CN104662614A

CN104662614A - Component cooling water system for nuclear power plant

Info

Publication number: CN104662614A
Application number: CN201380048906.4A
Authority: CN
Inventors: 克里希纳·P·辛格; 约瑟夫·拉杰库马尔
Original assignee: Smr Invention Technology Co Ltd
Current assignee: Smr Invention Technology Co Ltd; SMR Inventec LLC
Priority date: 2012-08-21
Filing date: 2013-08-21
Publication date: 2015-05-27
Also published as: WO2014031767A2; WO2014031767A3; KR20150045491A; EP2888742A2; JP2015529820A

Abstract

A component cooling water system for a nuclear power plant. In one embodiment, the system includes an inner containment vessel housing a nuclear reactor and an outer containment enclosure structure. An annular water reservoir is formed between the containment vessel and containment enclosure structure which provides a heat sink for dissipating thermal energy. A shell-less heat exchanger is provided having an exposed tube bundle immersed in water held within the annular water reservoir. Component cooling water from the plant flows through the tube bundle and is cooled by transferring heat to the annular water reservoir. In one non-limiting embodiment, the tube bundle may be U-shaped.

Description

For the component cooling water system of nuclear power station

The cross reference of related application

This application claims application number is 61/691,533, the applying date is the rights and interests of the U.S. Provisional Patent Application on August 21st, 2012, be application number be PCT/US13/42070, the applying date is the part continuation application of the pct international patent application on May 21st, 2013, this pct international patent application requirement application number is 61/649,593, and the applying date is the rights and interests of the U.S. Provisional Patent Application on May 21st, 2012; Its entirety is incorporated to herein by reference.

Technical field

The present invention relates to nuclear reactor, particularly relate to the containment system that there is passive Thermal release and control.

Background technology

The containment of nuclear reactor is defined as the shell utilizing the nuclear steam supply system (NSSS) of nuclear fission generation high pressure steam to provide environment to isolate to nuclear power station.Assuming that facility meets with the most serious nuclear accident, require commercial nuclear reactor to be closed in resist in the pressure holding structure from the temperature and pressure of this nuclear accident.Two classes can be had to the most severe energy release accident of reactor and containment supposition thereof.

The first, due to the unexpected release of reactor coolant in containment space, the heat energy rapid, high volume that the event with coolant loss accident (LOCA) relates to from Nuclear Power Station steam supply system (NSSS) discharges.The reactor coolant of unexpected decompression will cause the quick rising of pressure and temperature in containment space fiercely instantaneously.In containment, space becomes the mixing of air and steam.The pipeline catastrophic failure transporting reactor coolant by hypothesis is supposed LOCA credibly.

There is another Equations of The Second Kind incident heat of potential risk to be situation about all losing efficacy from all hot driving paths of the nuclear steam supply system (NSSS) of nuclear power station to containment entirety, force reactor " emergency shut-down (scram) ".The power-off of full station is exactly this event.The decay heat produced in reactor must be eliminated prevent pressure runaway and rise.

Recently, containment structure is also required by regulator the shock resisting crashed aircraft.Containment structure builds up huge reinforced concrete dome usually to resist the internal pressure from LOCA.Although its Concrete Thick wall can resist aircraft impact, but it is also good heat insulator, needs the cooling system (adopting heat interchanger and pump) being provided with pump to be discharged to by unwanted heat in external environment condition and (rise with minimum pressure or eliminate decay heat).But this cooling system relies on powerful power supply (e.g., the diesel-driven generator of strange land or this locality) to power for pump.After tsunami, the full station power-off of Fukushima nuclear power station is the thought-provoking prompting to the unwise behavior relying on pump.

The dismounting of the containment structure of present monolithic reinforced-concrete construction is exceedingly difficult and expensive, and the steam generator capital requirement as being enclosed in the NSSS in containment structure is huge.For changing visual plant, a hatch must be opened with huge expense and reactor Shutdown time on Concrete Thick dome.Unfortunately, the too many steam generator of the many nuclear reactors built in the past 25 years must, by penetrating dome to change, be the cost of multi-million dollar to Nuclear Power Industry.

In nuclear power station, parts chilled water (CCW) system is the closed loop pure water for cooling various equipment in nuclear power station.One of its important booster action from reactor water, discharges decay heat after reactor shutdown, is usually being called that the tubular exchanger inside of " decay heat cooler " or " Residual heat removal heat interchanger " performs.The heat that decay heat cooler or other heat interchanger for cooling electromechanical equipment are delivered to parts chilled water appears at whole tube wall, and this tube wall makes parts chilled water and may isolate with the radioactive contamination that reactor water is relevant or completely cut off.Like this, the means of device cooling system in essence for providing elimination to need all devices used heat in the nuclear power station of cooling, and be used as to hinder radiation to be discharged in environment.

But, its temperature of the heat lift collected from nuclear power plant equipment by parts chilled water.Usually by the shell-and-tube heat exchanger of use as natural waters such as lake, river or oceans, heat is discharged in environment in direct current (once-through) system by the parts chilled water heated.Component cooling water system extracts cold raw water from natural water, is pumped and flows through parts cooling water heat exchanger, then makes hot water turn back in natural water.But such component cooling water system (CCW) suffers from several operational issue, as the intrusion of residue of being carried by raw material chilled water, the biological pollution of the heat exchanger tube caused by raw water and transport the corrosion of raw water to the pipeline of heat interchanger.The frequent reported deposition thing of operating nuclear power station and other dirts accumulate in a large number in parts cooling water heat exchanger collector, need frequent maintenance and reduce thermal behavior.

The above-mentioned defect employing state-of-the-art technology needs nuclear reactor safety shell systems and the component cooling water system of improvement.

Summary of the invention

According on the one hand, the invention provides the component cooling water system overcoming existing system defect.

In one embodiment, the component cooling water system of nuclear power station comprises the containment limiting and be configured to the enclosure space holding nuclear reactor, around the containment enclosed construction of containment, be formed at the annular cistern between containment and containment enclosed construction, this annular cistern is configured to provide heating radiator for the heat that dissipates, and have be immersed in annular cistern water in exposed heat conduction tube bank without shell heat interchanger.Parts chilled water from nuclear power station flows through tube bank and is cooled by transferring heat to annular cistern.Tube bank is made up of many heat pipes.In one embodiment, tube bank is U-shaped.

In another embodiment, the component cooling water system of nuclear power station comprises the containment limiting and be configured to the enclosure space holding nuclear reactor, around containment enclosed construction and the annular cistern that is formed between containment and containment enclosed construction of containment, this annular cistern is configured to provide heating radiator for the heat that dissipates, the exposed heat conduction be made up of many heat pipes had in the water being immersed in annular cistern restrain without shell heat interchanger and the discharge spray thrower that is arranged in annular cistern below exposed tube bank.Spray thrower configures and is arranged through the water of tube bank discharge recycle from annular cistern with cooling duct.Parts chilled water from nuclear power station flows through the pipeline of tube bank and is cooled by transferring heat to annular cistern.

According to another embodiment, the component cooling water system of nuclear power station comprises the containment limiting and be configured to the enclosure space holding nuclear reactor, around containment enclosed construction and the annular cistern that is formed between containment and containment enclosed construction of containment, this annular cistern is configured to provide heating radiator for the heat that dissipates, the exposed heat conduction be made up of many heat pipes had in the water being immersed in annular cistern restrain without shell heat interchanger, with from containment to containment enclosed construction outwardly and be arranged in annular cistern be substantially radial multiple fins.In the present embodiment, heat interchanger is arranged in the gulf that circumference extends, and the gulf that this circumference extends is formed in the annular cistern between a pair isolated adjacent fins.Parts chilled water from nuclear power station flows through the pipeline of tube bank and is cooled by heat is passed to annular cistern.

According on the other hand, the invention provides and overcome the nuclear reactor safety shell systems that existing containment system arranges defect.This containment system generally comprises the internal security shell and external security shell seal structure (CES) that are made up of the material of steel or other flexibles, thus forms double-walled containment system.In one embodiment, between containment and the containment enclosed construction providing annular to cool cistern, water-filling ring cavity is provided.Containment can comprise multiple longitudinal heat transmission fin, and fin extends radially outwardly from containment with the shape of " fin " (substantially).Like this, containment is not only used as the main structure containment of reactor, and configuration and the heat interchanger that can be used between the annular cistern serving as heating radiator.Correspondingly, as further description, when needs time, during the thermal release accident of such as LOCA or reactor emergency shut-down need heat radiation and cooled reactor, containment provides passive (non-pumping) heat-extraction system easily.

The present invention also provides and overcomes the component cooling water system that existing cooling water system arranges defect.As further description, component cooling water system comprises the heat interchanger that can be arranged and be incorporated into water-filling ring cavity (that is, annular cistern).Therefore water in ring cavity be used as initiatively heat-conducting medium, gone out by the hot type in cooling system by evaporation instead of natural water.

At one according in embodiments of the invention, nuclear reactor safety shell systems comprises the containment being configured to hold nuclear reactor, around containment containment enclosed construction (CES) and be formed between containment and containment enclosed construction (CES), discharge the annular cistern of heat from containment space.If thermal release event occurs in containment inside, the heat trnasfer that containment produces is to the annular cistern for cooling containment.In one embodiment, annular cistern comprises the water of cooling containment.The part of containment can comprise heat transmission fin radially substantially, and it to be arranged in annular cistern and to extend to improve between containment and containment enclosed construction (CES) and dispels the heat to water-filling ring cavity cistern.When thermal release event occurs in containment inside, a part of water in ring cavity is evaporated with water vapour form by containment enclosed construction (CES) annular cistern and is discharged in air.

The embodiment of system also comprises auxiliary air cooling system, it comprise multiple in annular cistern the air conduit around containment band vertical portals circumferentially.The surrounding air fluid of the outside that air conduit is outside with containment enclosed construction (CES) with annular cistern is communicated with.When the water of thermal release event in the generation of containment inside and annular cistern exhausts substantially due to evaporation, air cooling system works by providing the air circulation path from cistern space to external environment condition.Like this, air flow system can be counted as the backup system that can continue repeatedly to cool containment.

According to another embodiment, nuclear reactor safety shell systems comprises the containment being configured to hold nuclear reactor, around the containment enclosed construction (CES) of containment, be formed at the cooling containment between containment and containment enclosed construction (CES) water-filling ring cavity and multiple from containment outwardly and be arranged in ring cavity be substantially radial fin.If thermal release event occurs in containment inside, the heat that containment produces is by contacting with containment outside surface and the direct of fin that be substantially radial cooling containment the water-filling cistern be sent in ring cavity.In one embodiment, when the water of thermal release event in the generation of containment inside and ring cavity exhausts substantially due to evaporation, air cooling system starts to work, and is drawn in ring cavity ambient air outside to cool the heat (exponentially declining in time) that containment produces by air conduit.The water existed in the annular region of containment completely will maintain the consistent Temperature Distribution of containment, prevents containment distortion during thermal release event or accident.

In another embodiment, nuclear reactor safety shell systems comprises the containment being configured to hold nuclear reactor containing garden cylindrical shell, around the containment enclosed construction (CES) of containment, be formed at the moisture annular cistern of the cooling containment between containment shell and containment enclosed construction (CES), multiple outside from containment protrude outwardly into ring cavity be substantially radial fin and containing multiple in annular cistern the air cooling system around the air conduit of containment band vertical portals circumferentially.Air conduit carries out fluid with annular cistern with the outside surrounding air of containment enclosed construction (CES) outside and is communicated with.If thermal release event occurs in containment inside, the heat that containment produces is that radial safe shell wall and its inside and outside fin being used as cooling containment are sent in annular cistern by (substantially).

Advantage and disadvantage according to nuclear reactor safety shell systems of the present invention comprises the following aspects:

Containment structure and system are configured to make above-mentioned thermal release event can Passive Shape Control (for example, not needing to rely on active devices, as pump, valve, heat interchanger and motor);

The containment structure of autonomous continuous working and system indefinitely;

In the major function not losing it (namely, pressure and radioactive nuclide (if any) keep and heat extraction) when, the containment structure strengthened with the inside and outside rib (fin) being configured to resist the struck by projectile such as the aircraft as crashed; With

Containment is equipped with and allows to be suitable for the facility by containment structure dismounting (or installation) visual plant.

Accompanying drawing is sketched

The feature of the illustrative embodiment of the present invention describes with reference to following accompanying drawing, the similar labelled notation of similar element, wherein:

Fig. 1 is the main reaction heap containment side view having fin according to a formation nuclear reactor safety shell systems part of the present invention, and the bottom of some fins is partially removed to appear vertical support column and circumferential rib;

Fig. 2 is the transverse sectional view of II-II along the line;

Fig. 3 is the detail drawing of III in Fig. 2;

Fig. 4 is containment and have the longitudinal sectional view of nuclear reactor safety shell systems of outer containment enclosed construction (CES) of the water-filling ring cavity shape cistern be formed between containment and containment enclosed construction in display Fig. 1;

Fig. 5 is the longitudinal sectional view by containment and containment enclosed construction (CES);

Fig. 6 is when installing with outer containment enclosed construction (CES), the side view of visible nuclear reactor safety shell systems on ground level;

Fig. 7 is its vertical view;

Fig. 8 is the longitudinal sectional view along the line VIII-VIII in Fig. 7, and display nuclear reactor safety shell systems is at the upper and lower two parts of ground level;

Fig. 9 is main reaction heap containment side view, and show cross section plane otch is to appear other details of in-built equipment and containment;

Figure 10 is its vertical view;

Figure 11 is the longitudinal sectional view along the line XI-XI in Figure 10;

Figure 12 is the longitudinal sectional view along the line XII-XII in Figure 10;

Figure 13 is the longitudinal sectional view along the line XIII-XIII in Fig. 9;

Figure 14 is the longitudinal sectional view along the line XIV-XIV in Fig. 9;

Figure 15 is the longitudinal sectional view along the line XV-XV in Fig. 9;

Figure 16 is nuclear reactor safety shell systems partial longitudinal sectional view, the cooling system that display is auxiliary;

Figure 17 is the isometric view of containment, and the bottom of the fin of (substantially) radial direction of containment is partially removed to appear vertical support column and circumferential rib;

Figure 18 is the longitudinal sectional view of a cooling system part in Figure 16, and display is attached to upper and lower ring-type collector and the conduit of containment shell;

During Figure 19 is thermal release event, the schematic description of the water-filling ring cavity shape cistern working condition of the cardinal principle xsect of nuclear reactor safety shell systems and heat radiation and cooling containment;

Figure 20 is the schematic cross sectional side view of a component cooling water system part according to a further aspect in the invention;

Figure 21 is the detail drawing amplified from Figure 20;

Figure 22 be in Figure 20 in component cooling water system from the vertical view of the first front elevation;

Figure 23 is the second vertical view from the first front elevation in component cooling water system in Figure 20, also schematically shows annular cistern recycle and water charging system;

Figure 24 is the side sectional view of heat interchanger in Figure 20; With

Figure 25 is the integral head cut-open view of nuclear reactor safety shell and component cooling water system.

Institute's drawings attached is all schematically and need not be proportional.

The detailed description of embodiment

With reference to illustrative embodiment, the features and advantages of the present invention are illustrated herein and describe.The description of illustrative embodiment is intended to understand by reference to the accompanying drawings, as a part for whole written description.In the description of embodiment disclosed herein, any direction related to or orientation are only intended to the convenience of description instead of are intended to limit the scope of the invention by any way.Relevant term, as " below ", " above ", " level ", " vertical ", " ... top ", " ... below ", " upwards ", " downwards ", " top ", " end " and (e.g., " flatly ", " down " derived from thus, " up ", etc.) should be interpreted as being called in nominal direction under discussion that there is described or show in figure.These relevant terms only for convenience of description, are not strict with facility and are built or operation with the concrete direction that term represents.Term, as " adding ", " attachment ", " connection ", " coupling ", " interconnection " and similar, refers to a kind of stabilized structure relation directly or indirectly through intermediate structure or the relations of dependence each other, also annex that is movable or rigidity or relation is referred to, unless otherwise described especially.Correspondingly, the present invention should not be particularly limited in such illustrative embodiment, and it illustrates some possible possible self-existent or nonrestrictive Feature Combinations in other Feature Combinations.

With reference to figure 1-15, show according to nuclear reactor safety shell systems 100 of the present invention.System 100 generally comprises inner containment structure, as containment 200, and the containment enclosed construction (CES) 300 of outside, jointly limit containment-enclosed construction assembly 200-300.Containment 200 and containment enclosed construction (CES) 300 vertically extend and orientation, and limit Z-axis VA.

In one embodiment, containment-enclosed construction assembly 200-300 is configured to be buried in ground, (also sees Fig. 6-8) at least partially under ground level.Containment-enclosed construction assembly 200-300 is by supporting by base plate 302 with from the concrete foundation that the vertically extending sidewall 303 that the base plate forming head substrate 304 rises forms.As shown, sidewall 303 circumferentially can close containment 200, and wherein the bottom of containment can be located in sidewall.In certain embodiments, be put into (first can being dumped and settling) after on base plate 302 at containment 200, sidewall 303 can be dumped, thus makes the bottom of containment 200 be embedded in basis completely.In embodiment shown in some, base wall 303 can stop with the supplementary protection provided containment-enclosed construction assembly 200-300 for struck by projectile (e.g., the aircraft etc. of crash) below ground level.In a top view, basis 301 can have any suitable layout, includes but not limited to polygon (e.g., rectangle, hexagon, circle etc.).

In one embodiment, the weight of containment 200 can support primarily of base plate 302, and containment rests on base plate 302, and the substrate 304 that containment enclosed construction (CES) 300 can be formed by sidewall 303 top on basis 301 supports.Also other suitable containers and containment enclosed construction support arrangement can be used.

Continue with reference to figure 1-15, containment structure 200 can be the container 202 of elongation, comprises the hollow cylindrical shell 204 of the circular cross section with outer dia D1, cover head 206 and bottom (head) 208.In one embodiment, containment 200 (that is, shell and end socket) can be made up (as mild carbon steel) of the sheet metal of the easy welding of proper strength and toughness and bar.In one embodiment, mild steel shell 204 can have the thickness of at least 1 inch.Other suitable metal materials can be used, comprise various alloy.

Cover head 206 is connected to shell 204 by bump joint 210, and bump joint 210 is made up of with the second coupling annular flange 214 being positioned at top on shell the first annular flange 212 being positioned at cover head lower end or bottom.Bump joint 210 can be bolt and connects, and the ring seal weld seam that can extend optionally by circumference further between contiguous flange 212 and 214 after mounting carries out welded seal.

The cover head 206 of containment 200 can be the end socket of the flanged and butterfly of ASME (ASME) dome shape to increase structural strength (i.e. internal pressure maintenance and external impact resistance); But, also can use other possible structures comprising flat cover head.Bottom (head) 208 can be the butterfly end socket of dome shape similarly or is selectively flat in the embodiment that other are possible.In a containment structure, bottom (head) 208 is directly welded to bottom or the end of shell 204 by the complete flanging of the end socket of matching can diameter.In one embodiment, as further description, the bottom of containment 200 can comprise the ribbed support 208a or similar structures that are connected to bottom (head) 208, be beneficial to firm and based on 301 base plate 302 on containment 200 horizontal support is provided.

In certain embodiments, the top 216 of containment shell 204 can be the part that shell is diametrically expanding, and forms the outer cover of the polar crane (not shown) supporting and hold for carrying equipment, fuel etc. in containment.This entrance that enters containment inner circumferential will be provided for crane and can make the placement of equipment from containment 200 edge very close to, make containment structure compact.Therefore, in a kind of structure, the ground level upper section of containment 200 can as mushroom construction.

In a possible embodiment, the outer diameter D 2 at the top 216 of containment 200 expansion is greater than the outer diameter D 1 of adjacent lower 218 remainder of containment shell 204.In a non-limiting example, about large than the diameter D1 of the bottom 218 of shell 204 10 feet of the diameter D2 at top 216.The top 216 of shell 204 can have suitable selected height H 2 to hold the polar crane needing workplace distance, and H2 can be less than 50% of the whole height H 1 of containment 200.In a non-limiting example, compared with the whole height H 1 of containment 200 feet, about 10 feet (H2) at containment 200 top are formed by the top 216 of enlarged diameter.The top 216 of containment 200 can stop on the top of flanged 214 with containment cover head 206 Flange joint.

In one embodiment, containment 200 is less than the internal diameter D3 of containment enclosed construction (CES) 300 at the diameter D2 at the top 216 diametrically expanded, to pass through one (substantially) radial gap or inner loop chamber 330 (e.g., seeing Fig. 4).When this arrives to the shock of containment enclosed construction in projectile, space buffer is provided or provides buffer area between containment enclosed construction (CES) 300 and containment top 216.In addition, as further description, ring cavity 330 creates flow channel significantly further between main ring chamber 313 (between containment enclosed construction (CES) 300 and containment 200) and the end socket space 318 between containment enclosed construction (CES) dome 316 and the cover head 206 of containment 200, flows out from containment enclosed construction (CES) for steam and/or air.Correspondingly, inner loop chamber 330 and main ring chamber 313 and alternately are communicated with through fluid the end socket space 318 that outlet 317 fluid of dome 316 is communicated with.In one embodiment, inner loop chamber 330 has less (substantially) radial width than main ring chamber 313.

With reference to figure 1-4, containment enclosed construction (CES) 300 can be double-walled construction in certain embodiments, have by (substantially) spaced radial and the sidewall 320 that formed of two concentric shells 310 interconnected (inner) and 311 (outsides), in its annular space between two concentric shells, normal concrete or reinforced concrete are installed.Concentric shell 310,311 can be made up of the material of any proper strength, as the sheet metal (as mild carbon steel) of the easy welding of (being not limited to) flexible.Other suitable metal materials can be used, comprise various alloy.In a nonrestrictive embodiment, double-walled containment enclosed construction (CES) 300 can have the thickness of the concrete 312 of 6 feet or larger, ensures enough to resist the ability of high energy struck by projectile, as from passenger plane.

Containment enclosed construction (CES) 300 defines the scope of containment shell 204 and radially separates with shell 204 (substantially), thus creates main ring chamber 313.Ring cavity 313 can be (i.e. the annular cistern) of water-filling in one embodiment to create heating radiator for receiving and eliminate the heat when thermal release event occurs in containment inside from containment 200.In one embodiment, this water-filling ring cavity shape cistern preferably circumference extend 360 ° around the circumference on containment shell 204 top be positioned at above concrete foundation 301.Fig. 4 shows the xsect of water-filling ring cavity 313, for clarity sake, and the fin 221 of (substantially) radial direction of the not shown outside of this figure.In one embodiment, ring cavity 313 is from being positioned at the substrate 304 of bottom 314 approximately to the concentric shell 310 of containment enclosed construction (CES) 300, the top 315 of 311 is full of water, to form annular cooling water cistern between containment shell 204 and the inner shell 310 of containment enclosed construction (CES) 300.In certain embodiments, the resistant material that annular cistern can be coated with or liner one deck is suitable, as aluminium, stainless steel, or suitable for etch-proof antiseptic.A representativeness, in nonrestrictive example, ring cavity 313 can wide about 10 feet and height about 10 feet.

In one embodiment, containment enclosed construction (CES) 300 comprises steel dome 316, and it is suitably thick and is reinforced to resist aircraft and other projectiles attacked of crash.Dome 316 is removably fixed on shell 310, on 311 by firm bump joint.In one embodiment; full shell enclosed construction (CES) 300 is surrounded by containment enclosed construction (CES) 300 entirety with upper part at all exposed ground levels; it is preferably enough high to protect containment to resist the dangerous or similar projectile of aircraft, keeps the structural intergrity of water body in the ring cavity 313 of containment.In one embodiment, as shown, containment enclosed construction (CES) 300 extends vertically up to solid part at a distance until the top of substrate 304 below ground level.

Containment enclosed construction (CES) 300 can comprise at least one rainproof outlet 317 further, outlet 317 is communicated with fluid between the end socket space 318 below dome 316 and water-filling ring cavity 313, to allow mathematical models, overflow and be discharged in air.In one embodiment, the center that 317 can be positioned at dome 316 is exported.In certain embodiments, outlet 317 can be formed by a short segment pipe, pipeline covers the canopy of any suitable construction, and permission steam is overflowed from containment enclosed construction (CES) 300, but makes the water that enters minimum.

In the embodiment that some are possible, end socket space 318 between dome 316 and the cover head 206 of containment 200 can insert energy-absorbing material or structure with make crash (landing) projectile (as, aircraft, etc.) minimum to the impact load of containment enclosed construction (CES) dome 316.In one example, closely compress corrugated or have deformable multiple aluminium sheet of fold can be located at a part or whole part in end socket space to form fold buffer zone, is beneficial to and absorbs and the impact of dissipation to dome 316.

Primary Reference Fig. 1-5 and Fig. 8-17, the buried portion below substrate 301 with the containment 200 of concrete foundation 301 can have the common enclosure without surface.But the part of containment shell 204 above substrate 304 can comprise multiple longitudinal (substantially) outer radial rib or fin 220, its axial (substantially) is parallel to the Z-axis VA of containment-closed component 200-300.Outside longitudinal fin 220 arranges around the circumference circumference interval of containment shell 204 and extends from containment outside (substantially) radial direction.

Rib 220 provides multiple useful function, include but not limited to that (1) makes containment shell 204 hard, (2) water when preventing seismic events in ring cavity 313 undue " rocking (sloshing) ", (3) when there is liquid/steam release event in containment, significantly as heat conduction " fin " for the dissipation of heat that the conduction by shell 204 is absorbed in the environment of ring cavity 313.

Correspondingly, as further description, in an embodiment making heat-conducting effect best, the generallyperpendicular whole height extending to water-filling ring cavity 313 of outside longitudinal fin 220, cover the effective heat-transfer surface (that is, non-buried part in concrete foundation) of containment 200 heat to be sent to cistern from containment 200.In one embodiment, outside longitudinal fin 220 has top water flush end 220a and lower horizontal end 220b, top water flush end 220a ends at or closest to the downside at the larger diameter top 216 of containment 200 or bottom, and lower horizontal end 220b ends at or closest to the substrate 304 of concrete foundation 301.In one embodiment, the height H 3 of outside longitudinal fin 220 is equal to or greater than the half of the whole height of containment shell.

In one embodiment, the top water flush end 220a of longitudinal fin 220 is free ends, and impermanent connection (as welding) is to containment 200 or other mechanisms.At least part of of lower horizontal end 220b of longitudinal fin 220 contacts adjacently and rests on the rib 222 being welded on containment shell 204 outside surface of circumference of level, and the weight being beneficial to support longitudinal fin 220 is minimum with the pressure making to act on longitudinal rib-shell pad.Circumferential rib 222 is annular and can intactly extends 360 ° around the circumference of containment shell 204.In one embodiment, circumferential rib 222 is oriented to rest on the substrate 304 of concrete foundation 301, and the load of longitudinal fin 220 is sent to basis.Longitudinal fin 220 can have horizontal length or width, outwardly exceeds the neighboring of circumferential rib 222.Correspondingly, in this embodiment, the interior contact circumferential rib 222 of the only lower horizontal end 220b of each rib 220.In the embodiment that other are possible, circumferential rib 222 can (substantially) radially stretch out enough far away, so that the whole lower horizontal end 220b of each longitudinal rib 220 rests in circumferential rib 222 substantially.In certain embodiments, lower horizontal end 220b can be soldered to circumferential rib 222 to make longitudinal rib 220 strengthen further or firm.

Outside longitudinal fin 220 can be made up (as mild carbon steel) of steel, or other suitable metal materials, comprises alloy, and each fin 220 side extending longitudinally is welded to the outside of containment shell 204.The side that each rib 220 reverse portrait extends be in closest to, but be preferably connected to the inside of the inner shell 310 of containment enclosed construction (CES) 300 non-permanently, to make the heat-transfer surface of the rib as radiating fin maximum.In one embodiment, outside longitudinal fin 220 (substantially) radially stretches out and exceeds the larger diameter top 216 of containment 200, as shown.A representativeness but in nonrestrictive example, steel rib 220 can have the thickness of about 1 inch.Other suitable thickness of rib can be used as one sees fit.Correspondingly, in certain embodiments, the radial width that rib 220 has is greater than 10 times of rib thickness.

In one embodiment, in oblique angle A1 between the orientation of longitudinal fin 220 and containment shell 204, as shown in Fig. 2-3 and Fig. 5 the best.The party is to formation folded region, and the circumference around containment 200 extends 360 °, to improve the function resisting struck by projectile together with outer containment enclosed construction (CES) 300.Correspondingly, make containment enclosed construction (CES) 300 shell 210, the shock of the internal modification of 211 will make longitudinal fin 220 bend, impact will be distributed better in this process, directly can not be transferred to internal security shell shell 204 and make it rupture, may occur between rib and containment shell 204 in 90 ° of orientations simultaneously.In the embodiment that other are possible, depend on structure and other factors of containment enclosed construction (CES) 300, being arranged vertically relative to containment shell 204 of rib 220 is appropriate.

In one embodiment; with reference to figure 6-8; containment shell 204 be may extend into below ground level by the part that the fin 220 that outside (substantially) is radial protects to resist struck by projectile; to provide protection at ground level or a little less than ground level place, resist the shock of projectile to containment enclosed construction (CES) 300.Correspondingly, substrate 304 is formed at vertically extending sidewall 303 top on basis 301, and the fin 220 ending at their lower end can be located at below ground level several feet, to improve the shock resistance of nuclear reactor safety shell systems.

In one embodiment, containment 220 comprises the multiple fins 221 (as shown in dotted line in Fig. 2 and 3) being connected to the inside surface of shell 204 of inside (substantially) radial direction of circumferentially spaced alternatively.Inner fins 221 (substantially) radially from containment shell 204 and longitudinally extends internally in the vertical direction of a suitable height.In one embodiment, the fin 221 that inner (substantially) is radial can have the height the top extending to about shell 204 from substrate 304 that prolong together (coextensive) substantially with water-filling ring cavity 313.In a nonrestrictive embodiment, inner fins 221 can be oriented to vertical with containment shell 204 (that is, 90 °) substantially.Also other suitable angle and tilted alignments can be used.Inner fins is used as increase effective surface area and structure to strengthen containment shell and resists external impact (as projectile) or the increase of the internal pressure in containment pressurization event situation in containment 200 (as LOCA or reactor emergency shut-down).In a nonrestrictive embodiment, inner fins 221 can be made up of steel.

With reference to figure 1-15, multiple vertical stratification support columns 331 can be connected to the outside surface of containment shell 204, contribute to supporting the top 216 of diametrically larger containment 200, support column 331 has neighboring, as cantilever (substantially) radially outwardly exceeds shell 204.Support column 331 is circumferentially spaced apart about the disc around the border of containment shell 204.In one embodiment, support column 331 can be made up of the steel structure member of hollow, as being not limited to the component (that is, structure channel) of C-shape xsect, is soldered to the outside surface of containment shell 204.The parallel supporting leg of two, this passage can adopt continuously along the height of each support column 331 or interrupted welding (as seam weldering) is soldered to containment shell 204.

Support column 331 extends vertically downward and is soldered to the bottom/downside at the top 216 of the larger diameter of the containment holding polar crane on its top.The bottom of support column 331 leans on or is welded in circumferential rib 222, and rib 222 engages with the substrate 304 of the concrete foundation 301 near containment buried portion.Support column 331 contributes to being transferred to basis downwards by from a part of quiescent load of crane and containment 300 top 216 or weight.In one embodiment, the space of support column inner hollow can fill concrete (having or no-reinforcing-bar), to make its firm and further support quiescent load or weight.In the embodiment that other are possible, the shaped steel of other structures can be used, comprise filling or unfilled case beam, I-beam, steel pipe, angle steel etc.Longitudinal fin 220 can extend outwardly beyond support column 331 further on the direction that (substantially) is radial, provides structural effect, instead of the conductive force as rib 220.In the embodiment determined, (substantially) radial width of rib 220 is at least the twice of (substantially) radial width of support column.

Figure 11-15 shows the various xsects (longitudinal with transverse direction) of the containment 200 of the equipment of including.In one embodiment, containment 200 can be a part for small modular reactor (SMR) system, as the SMR-60 by Hall Tyke international corporation.Equipment generally can comprise with reactor core and the nuclear reactor pressure shell 500 being located at the circulation primary cooling medium in wet-well 504, and the steam generator 502 be connected with reactor and circulation secondary coolant fluid, forms a part for Rankine power generation cycle.Other adjuncts and equipment can be provided to create complete steam generating system.

Present Primary Reference Fig. 2-3,16 and 18, containment 200 can comprise auxiliary heat dissipating system 340 further, comprises the spaced apart multiple inner longitudinal duct 341 of circumference around containment shell 204.Conduit 341 is parallel to Z-axis VA and vertically extends, and is connected to the inside surface of shell 204 in one embodiment.Conduit 341 by metal, as steel are made, and can be soldered to the inside surface of shell 204.In a possible nonrestrictive structure, conduit 341 can be made up of vertical orientated C-shape (xsect) structure channel, so that the whole height of the parallel supporting leg of this passage is all soldered to shell 204, to limit the perpendicular flow pipeline of sealing.The conduit of other suitable shapes or structure can be provided so long, makes the fluid contact internal security shell shell 204 carried in the catheter at least partially, to conduct heat to water-filling ring cavity 313.

Any suitable quantity of conduit 341 and layout depend on that the heat conduction surface area of the fluid of conduit is flow through in needs cooling.Conduit 341 homogeneously or heterogeneously can be arranged in the inside of containment shell 204 in interval, and in certain embodiments, conduit bunch in groups can around the distribution of containment circumference.Depend on flow rate and the heat conduction factor of the fluid carried by conduit, any suitable xsect size that conduit 341 can have.

The equal fluid of the upper and lower side 341a of conduit 341 opening, 341b is connected to common top input ring collector 343 and bottom output ring collector 344.The ring collector 343 of annular, 344 are vertically separated and are located at containment 200 inside at appropriate heights, maximize with the heat conduction between the fluid of perpendicular flow in conduit 341 and the shell 204 of the containment in movable thermal conductive zone, this movable thermal conductive zone is limited by some parts of the containment in main ring chamber 313 with outside longitudinal fin.For utilizing the heat conduction of main water-filling ring cavity 313, upper and lower ring collector 343,344 can be located at the inside of containment shell 204 separately respectively, adjoins and near the top of ring cavity and bottom.

In one embodiment, ring collector 343,344 all can be formed by shown multiple half section of steel pipe, is directly welded to the inside surface of containment shell 204 in the manner shown.In other embodiments, ring collector 343,344 all can rely on and formed in any way as suitable by the pipeline of shell 204 inner support and whole section of bow action being connected to shell 204 inside.

In one embodiment, cooling system 340 fluid is connected to vapour source, and this vapour source may result from the water body for discharging radiomaterial decay heat of containment 200 inside.The containment surface surrounded by conduit 341 is used as heat-transfer surface, the latent heat of steam in conduit to be delivered to the shell 204 of containment 200, is cooled by outside longitudinal fin 220 and water-filling ring cavity 313.In the course of work, steam enters input ring collector 343 and is assigned to the opening input end of the conduit 341 through ring collector.Steam enters conduit 341, and the internal height wherein along containment shell 204 flows downward and experiences liquid-gas phase transition.In one embodiment, the steam of condensation flows down in the catheter due to gravity and preferably also turns back to vapour source by gravity after being collected by bottom ring collector 344.It should be noted that in above-mentioned process and do not relate to or need pump.

According to a further aspect in the invention, if due to some reasons, during thermal reactor dependent event (as, LOCA or reactor emergency shut-down), storage water in main ring chamber 313 is depleted, and auxiliary or passive null air cooling system 400 for subsequent use is provided for sets up Air flow by the natural convection of containment 200.With reference to figure 8, air cooling system 400 can be made up of the multiple vertical input air conduit 401 laid around containment 200 circumferentially spaced in main ring chamber 313.Each air conduit 401 comprises entrance 402 through containment enclosed construction (CES) 300 sidewall 320 and air to the outside opens wide the cooling-air that extracts in environment.Entrance 402 is preferably arranged on the upper end of the sidewall 320 near containment enclosed construction.Air conduit 401 extends downward vertically in ring cavity 313 inside and a short distance (as about 1 foot) above the substrate 304 on basis stops, and overflows from conduit bottom to allow air.

Use air conduit 401, in conjunction with ring cavity 313, set up natural convection cooling draught path.If the storage chilled water in main ring chamber 313 is because evaporation exhausts during incident heat, when ring chamber air continues to be heated by containment 200, Air flow is worked automatically by natural convection.Hot-air in main ring chamber 313 rises, and by inner loop chamber 330, enters end socket space 318, and flows out the dome 316 of containment enclosed construction (CES) 300 by outlet 317 (see flow arrows in Fig. 8).The hot-air risen makes the air pressure bottom relative to main ring chamber 313 be reduced to and enough extracts ambient air outside downwards by air conduit 401, thus creates the containment 200 that natural air circulation pattern continues the heat of cooling.Advantageously, this passive null air cooling system and circulation sustainable cooling indefinitely containment 200.

It should be noted that main ring chamber 313 is used as the primary heating radiator of the heat that containment 200 inside produces.Water in annular cistern is also for maintaining substantially identical temperature by the temperature of all crane vertical support column 331 (describing) before, so under any circumstance, the levelness of the crane rail (not shown) of the greater part being arranged on containment 200 is guaranteed.

Containment system 100 briefly describes referring now to Figure 19 as the operation of heat interchanger.This figure is the graphic representation of the simplification of containment system 100, for clarity sake, does not describe all devices and structure when this is in the active thermal conduction and radiation processes that describe and performed by this system.

Under coolant loss (LOCA) accident conditions, high-energy fluid or liquid coolant (typically water) are splashed into the containment environment formed by containment 200.Liquid becomes steam instantaneously, and in containment, water vapour mixes with air and transfers to the inside surface (because the containment shell facing water in ring cavity 313 is colder) of containment 200 sidewall or shell 204.Then water vapour passes through by its latent heat treatment to containment structure metal, and vertical enclosure wall condenses, and the exposed part that containment structure metal wheel flows through longitudinal fin 220 and ring cavity inside and outside shell 204 discharges heat in the water of ring cavity 313.Water heating in ring cavity 313 also finally flashes to water vapour, and water vapour rises and passes through inner loop chamber 330 in ring cavity, end socket space 318 and leave containment enclosed construction (CES) 300 in air finally by outlet 317.

When the cistern in ring cavity 313 is positioned at containment environmental externality, in certain embodiments, external device (ED) (if present) is adopted storage water can be supplemented easily with the vaporization loss of compensation water.But if to provide without make-up water or available, then the water colunm height in ring cavity 313 will start to reduce.When ring cavity 313 middle water level reduces, containment 200 also starts to heat the air above ring cavity middle water level, thus discharges part heat to air, and air rises and passes through outlet 317 and flows out from containment enclosed construction (CES) 300 with water vapour.When water level reduces suddenly, cause the open bottom end of air conduit 401 (e.g., seeing Fig. 8) exposed above waterline, as mentioned above, fresh ambient air outside then will be sucked into from air conduit 401, to set up natural convection air circulation mode, continue cooling containment 200.

In one embodiment, facility (as water pipeline) is provided for the water in supplementary ring cavity 313 by containment enclosed construction (CES) 300, although do not need to ensure enough dissipation of heats.In annular cistern, how many total amounts of storage water is determined, like this, the decay heat produced in containment 200 reduces fully, once storage water exhausts, containment can by its all warm of independent air cooling discharge.Containment 200 preferably has enough heat removal capacities, with the pressure and temperature (in its limiting design value) by discharging the water vapor mixture in caloric restriction containment fast.

Under the powering-off state of full station, reactor core is forced to " emergency shut-down ", and passive core cooling system will discharge the decay heat (as seen Figure 16 and 18) of reactor core with the vapor form of the top input ring collector 343 of the cooling system 340 described that leads.The steam flowed downward by inner longitudinal duct 341 network subsequently contacts containment shell 204 inside surface be enclosed in heat radiation conduit, and condense by discharging its latent heat to containment structure metal, the heat conduction utility appliance that containment structure metal wheel flows through to be provided by longitudinal fin 220 discharges heat in the water of ring cavity 313.The final heating evaporation of water in annular cistern (main ring chamber 313).Containment 200 is by feeling heating, subsequently by evaporation and Air flow mixing, then final further by means of only described natural convection Air flow, discharges heat in ring cavity.As mentioned above, containment system 100 is designed and is configured to once effective storage water exhausts completely in ring cavity 313, and independent air cooling just enough discharges decay heat.

In aforementioned two kinds of situations, can ad infinitum heat extraction continuously, until occur that replacement device is resumed operation for making nuclear power station.Not only system ad infinitum operates, and this running is passive completely, does not need to use any pump or operator to intervene.

Component cooling water system

Another aspect according to Figure 20-25 of the present invention, provides parts chilled water (CCW) system 600 of improvement.Relative to direct current (once-through) cooling system that utilization before cools from the raw water of natural water, component cooling water system 600 generally comprises heat interchanger 610 and one or more parts cooling-water pump 601 be fluidly connected by the recirculation cooling water pipe ring 636 of base closed.Major part cooling water pipeline ring 636 can be located at nuclear reactor safety shell 200 and around (as seen Figure 25) in the nuclear power station of containment enclosed construction 300 outside of containment.Cooling water pipeline ring 636 collects the chilled water of heating and cooling from the nuclear power station support equipment (by CCW box indicating Figure 25) that fluid is connected to pipe ring and component cooling water system 600, and the chilled water of heating and cooling is assigned to nuclear power station support equipment.Pump 601 provides power for driving current by pipe ring 636 and heat interchanger 610.Pump 601 can be the pump (e.g., centrifugal pump etc.) of any suitable type, has suitable water suction and setting-out lift for application conditions and expectation flow rate.Any quantity or the layout of pump 601 is provided, for recirculated cooling water by pipe ring 636.

According to one embodiment of present invention, component cooling water system 600 utilizes easily and is formed at water in water-filling ring cavity between internal security shell 200 and outer containment enclosed construction 300 (aforesaid) 313 (herein or be called annular cistern 313) as useful heat-conducting medium or heating radiator, conducts heat to annular cistern and component cooling water system 600 or from annular cistern and component cooling water system 600 heat conduction.Correspondingly, in this embodiment, heat interchanger 610 can be located at completely and immerse/be submerged in annular cistern, for direct heat conduction to cistern.Generally speaking, as further description, in the flowing ring closed of cooling water pipeline ring 636 between annular cistern 313 and nuclear power station cooling device, recirculation hardware chilled water.

Start with reference to Figure 24, in a nonrestrictive structure, the heat interchanger 610 of component cooling water system 600 is without shell heat interchanger, comprise the opening up U-shaped tube bank 611 of vertical elongated and orientation, U-shaped tube bank 611 is made up of multiple U-shaped heat pipe 620, and U-shaped heat pipe 620 two ends are all connected to the tube sheet 612 of adjacent channel 613.Passage 613 is limited with inner space, and it is divided into input room 614 by vertical partition plate 616 and exports room 615.The bottom of I/O room 614,615 is formed by the upside of tube sheet 612.The top of I/O room 614,615 is closed by the top cover 618 being detachably connected to passage 613 upper end.

Heat interchanger 610 is comprised and is connected to the inlet nozzle 630 of input room 614 by the sidewall fluid of passage 613 and is connected to by the sidewall fluid of passage and exports the outlet nozzle 631 of room 615.In one embodiment, entrance and exit nozzle 630,631 can be located on passage 613 toward each other, but other suitable layouts are possible.Entrance and exit nozzle 630,631 fluidly connects the input cooling water pipeline 632 of heat interchanger 610 to component cooling water system 600 and exports cooling water pipeline 633.Input and output cooling water pipeline 632,633 is fluidly connected to the cooling water pipeline ring 636 (also seeing Figure 25) closed of component cooling water system 600 in turn.In one embodiment, entrance and exit nozzle 630,631 can be provided with flange, for being connected to the plain flange being located at input and output cooling water pipeline 632,633 port.Bump joint 617 between nozzle and pipeline can be fixed with bolt in one embodiment, or is welded and fixed in other embodiments.But, should be appreciated that this input and output cooling water pipeline 632,633 can directly be welded to entrance and exit nozzle 630,631 without flange.The fluid connection type of any suitable type can be used.

In certain embodiments, input and output cooling water pipeline 632,633 can be arranged to extend through the breakthrough portion 635 (as seen Figure 22) formed by outer containment enclosed construction 300 of suitably configuration.Any suitable height can be located in breakthrough portion 635, with the entrance and exit nozzle 630,631 allowing cooling water pipeline to be connected to heat interchanger 610.Pipeline can be any suitable metal or nonmetal pipeline.

In one embodiment, the bump joint 617 that bolt is fixing can be used to removably top cover 618 is fixed to passage 613.But other suitable methods also can be used for connecting top cover 618 to passage 613.Top cover 618 provides the leakproof seal of passage 613 and can comprise suitable packing ring and/or sealing gasket to form watertight connection, as will be well known to those skilled in the art.Preferably, dividing plate 616 configures and is arranged as with the lower side engagement of tube sheet 612 and top cover 618 and forms sealing.This is intended to prevent or at utmost reduce in the input room 614 of dividing plate 616 opposite side and the leakage exporting chilled water between room 615.In a possible layout, dividing plate 616 can have linear bottom or edge, when top cover is arranged on passage 613, via suitable packing ring and/or sealing gasket, dividing plate 616 can by the linear apices that is welded to the upside of tube sheet 612 securely and removably engage with the downside of top cover 618 or edge.Moveable top cover 618 is provided to the entrance of channel interior tube sheet 612, for inserting leakage pipe, performs the Non-Destructive Testing to tube sheet and pipe and inspection, or for other objects.

Primary Reference Figure 20-25, especially Figure 24, in a typical embodiment, heat interchanger 610 can be without shell heat interchanger, wherein U-shaped pipe 620 is not closed and exposed, directly immerses or is submerged in the water-filling ring cavity 313 of the nuclear reactor safety shell systems 100 be formed between internal security shell 200 and outer containment hermetically-sealed construction 300.Pipe 620 all can comprise two line parts 621 and one and be located at tube sheet 612 end and at the U-bend pars convoluta 622 of tube sheet 612 opposite side.Each pipe 620 is had and is connected to the first end 623 of the line part 621 of input room 614 by tube sheet 612 and is connected to the second end 624 of line part exporting room 615 by tube sheet.In one embodiment, the end adjoining the pipe 620 of pipe end can be extended by the vertical through hole being formed at tube sheet 612 from the downside of tube sheet to top side completely.Pipe is fixed to tube sheet 612 by any suitable mode, includes but not limited to welding, and the explosivity of the relative tube sheet of tube end expands, or other methods known in the art.

U-shaped pipe 620 can be exposed or selectively comprise fin (as axis or spiral), depend on that the heat flux of expection application requires and other technologies factor.Pipe 620 can by any suitable iron or the metal or metal alloy of non-ferric make, as nonrestrictive example, attachment is aluminized or the aluminium of solid Stainless Steel Tubular Plates 612 or steel pipe respectively.Preferably, pipe 620 can be selected corrosion resistant.Pipe 620 can have any suitable external diameter and wall thickness.

With reference to figure 20-25, the heat interchanger 610 illustrated is arranged on around (annular cistern) in the water-filling ring cavity 313 of internal security shell 200.Water in annular cistern remains on nonstatic state by the recirculation pump 663 of cistern recirculating system 662 (see Figure 23), and recirculation pump 663 draws water and makes water return ring cavity 313, agitate water from ring cavity 313, thus prevents algae from growing.These pumps also can be used for filtering incessantly water in cistern to maintain its cleanliness.In annular cistern 313, the motion of water is also beneficial to and promotes evaporation, contribute to any cooling effect owing to it, remove as coolant loss accident (LOCA) heat or in reactor normal work period, remove heat by the heat interchanger 610 be submerged in cistern from the chilled water of component cooling water system.

In one embodiment, heat interchanger 610 is suspended in water-filling ring cavity 313 (to be had suitable shock resistance) and locates, so that the bottom (being limited by U-shaped pipe 622) of restraining 611 separates laying with vertical range V1 above annular cistern, as shown in figs 20 and 21.In a non-limiting layout, heat interchanger 610 comprises anchor or the support member 640 of one or more radial direction extension, preferably be connected to passage 613 with rigid manner, when being connected to the movement of the structural elements in annular cistern (following) limit passage.This layout limiting channel 613, but advantageously, at component cooling water system 600 duration of work, when the temperature variation according to the parts chilled water of flowing in pipe 620, when pipe 620 is heated or cooled, allow tube bank 611 length relative to passage 613 spread and shortening without restrictions.In a typical embodiment, support member 640 can be formed by the structural steel and iron of the horizontal alignment reinforced by vertical reinforcing plates being welded on leveling board and passage 613 side.Heat interchanger support member 640 many other change and configuration be possible and can be used.

Support member 640 can be installed to the containment-enclosed construction assembly 200-300 in water-filling ring cavity 313 by various ways.In one example, support member 640 can be fixed or be welded in place in water-filling ring cavity 313 inside and be connected to the structural support 641 of the correspondence of containment-enclosed construction assembly 200-300 by bolt.In various embodiments, support member 641 can be pedestal type, as shown in some non-limiting examples, rise from the bottom 642 of annular cistern, give prominence to (see 641 Figure 21) from the inside surface cantilever of the steel inner shell 310 of outer containment hermetically-sealed construction 300, or its combination.Other changes many of support member 641 optionally provide.Support member 641 can be made up of any suitable material or combination of materials, comprises steel, concrete, or other.Preferably, heat interchanger support member and susceptor design and be arranged as earthquake stability is provided water-filling ring cavity 313 in the installation of heat interchanger 610.

With reference to figure 20-25, heat interchanger 610 can be placed and be suspended on the correct position in one of " gulf " 650, and " gulf " 650 is formed in water-filling ring cavity 313, and water-filling ring cavity 313 to adjoin for a pair between the fin 220 separated.In arranging at one, heat interchanger 610 can be positioned near annular columns base 642, so that sustainable heat transfer when as possible, as when the water level in ring cavity 313 reduces due to evaporation, if the offhand make-up water to cistern and the emergency shut-down event that occurs.

In one embodiment, preferably, the gulf 650 at heat interchanger 610 place is in a position, in this position, the discharge spray thrower 664 that the recirculation pump 663 of at least one annular cistern recirculation conduit system 662 makes water flow through to place, to stir water body around exposed tube bank 611.By contrast, different from the position that flow condition possible in other gulfs 650 is relatively more stagnated, this layout is intended to improve by pipe and flowing between the tubes, with increased thermal conductivity energy.Recirculation pump 663 is drawn water from annular cistern 313 by the efferent duct 661 being connected to cistern at a correct position fluid, is connected to input pipe 660 discharge water of the spray thrower 664 immersing/be submerged in cistern by fluid.In certain embodiments, input and output pipe 660 and 661 can extend across the suitable breakthrough portion 635 formed by the sidewall of outer containment hermetically-sealed construction 300; But in the layout that other are possible, input pipe can enter spray thrower 664, as the top (as from its plan vertical in annular cistern to the pipeline of downward-extension) from annular cistern 313 from except the position guiding recirculation water by sidewall.Efferent duct 661 can aspirate from annular cistern 313 in any suitable position, as without limitation in the identical gulf 650 comprising spray thrower 664 or different gulfs.

Recirculation pump 663 can be any suitable type pump (as centrifugal etc.), and it is for application conditions and expect that flow rate has suitable water suction and setting-out lift.Pipeline can be any suitable metal or nonmetallic pipeline.In various embodiments, more than one cistern recirculation conduit system 662 and/or spray thrower 664 can be provided.

With reference to Figure 21 and 23, in certain embodiments, spray thrower 664 can be formed by the collector with multiple supine delivery outlet 665 separated by any suitable interval of usual horizontal alignment.In a preferred embodiment, spray thrower 664 is positioned at heat exchanger tube 661 vertical lower and upwards discharges recirculation water in tube bank.Spray thrower 664 can be laid with any suitable distance interval below tube bank 661.Spray thrower creates cistern water and upwards flows in the local of its overlying regions, and contributes to extracting extra water formation recycle upwards flow pattern from cistern.According to teaching discussed herein, it is possible that alternative spray thrower is arranged.

In certain embodiments, annular cistern 313, preferably further in a position, is injected at this position " cold " make-up water in the gulf 650 of mounting heat exchanger 610, evaporates the dehydration caused to supplement from cistern.The local repair feedwater entering the gulf 650 near heat interchanger 610 enhances the cooling of the parts chilled water of heat conductivility and heat.As shown in figure 23, makeup Water System 670 can comprise make-up pump 671, and it is outwards drawn into annular cistern 313 from any suitable nourishment source and makes make-up water drain into annular cistern by input pipe 672.Input pipe 672 can be arranged in any suitable position, gulf 650, does not disturb the flow pattern produced by spray thrower 664 in this position, but enough near heat interchanger 610, to obtain the heat conductivility benefit of the water roughly colder compared to the water in annular cistern 313.Input pipe 672 can extend across the breakthrough portion 635 formed by the sidewall of outer containment hermetically-sealed construction 300; But in the layout that other are possible, input pipe can from the position be different from by sidewall, as from the top of annular cistern 313 (as from annular cistern by the pipeline of its plan vertical to downward-extension), introduce supplementing water.Pump 671 can be the pump (e.g., centrifugal etc.) of any suitable type, and it is for application conditions and expect that flow rate has suitable water suction and setting-out lift.Pipeline 672 can be any suitable metal or nonmetallic pipeline.

Should be appreciated that Comparatively speaking the term " cold " about make-up water is, be often referred to the fact that make-up water obtains from the external water source beyond annular cistern, and preferably there is the temperature being usually less than water temperature in annular cistern 313.Some water are converted to water vapour due to the nuclear reactor running in containment vessel, these water vapours flow out to air from containment vessel, as described herein, so the water in annular cistern typically can have the temperature higher than environment.Under the nuclear power station condition of work determined, make-up water may have and to equal and even higher than the temperature of the water temperature changed in annular cistern.Correspondingly, term " cold " for the object herein for describing, to describe makeup Water System better, but not as restricted term.

In the normal mode of operation of reactor and component cooling water system 600, the hot water received from the nuclear power plant equipment that various fluid is connected to component cooling water system by parts cooling-water pump 601, heat interchanger 610 (with reference to Figure 22,24 and 25) is pumped to by coolant intake pipe 632.The chilled water of heat flows to the input room 614 of heat interchanger 610 by inlet nozzle 630.Then the chilled water of heat is flowed downward by the pipe 620 of tube sheet 612 and tube bank 611, reverse via pipe bend 622, is flowed up into the output room 615 in passage 613 by pipe.In pipe 620, the chilled water of the heat of flowing is by being cooled the heat transfer on tube wall to the water in water-filling ring cavity 313 (annular cistern).The chilled water turned cold now is flowed by the efferent duct 635 being connected to heat interchanger 610 from output room 615 and is back to component cooling water system 600 subsequently, is equipped with the various nuclear power plant equipment of cooling for dividing.Entering cistern water body by heat interchanger 610 stored in the thermal diffusion in annular cistern and be heated, being dissipated in environment eventually through from containment system 100 to the evaporation of environment, as described herein.In one embodiment, the water vapour from the heating of annular cistern 313 flows in environment by the outlet 317 on the dome 316 of containment hermetically-sealed construction 300.

Direction arrow shown in figure represents the flow path of the fluid discussed with reference to each figure herein.One skilled in the art will appreciate that fluid-duct-system described herein can comprise the various necessary utility appliance by complete function system and annex, as valve, filtrator, pressure governor, flow and pressure indicator, support of pipelines etc.

Heat interchanger 610 be described to exemplary but nonrestrictive have U-shaped Pipe bundle structure without shell heat interchanger, owing to being only single split passage 613, and heat-transfer tube farthest exposes along its vertical edges and the end to annular cistern 313, to be optimized flowing through tube bank, this has the following advantages without shell heat interchanger, such as: compact conformation, low cost of manufacture (material and processing).But, should be appreciated that and other can be used to make pipe be exposed to tubular construction (as without shell heat interchanger) in the water of annular cistern 313.Other possible structures can be included in the straight line tube bank that each pipe end place between the input and output passage that separates and relatively lay connects.Will be further understood that, except vertical, other orientations of tube bank can be adopted, as level or angled between vertical and horizontal.Correspondingly, the present invention is not subject to the restriction of heat exchanger structure and orientation.

This neoteric advantage comprises: eliminate and to supply water to the apparatus cools heat interchanger in current nuclear power station and to be well-knownly subject to corrosion of elements and aging long diversion line, and the heating surface caused with raw water Long contact time that heat exchanger tube can not be subject to perplexing current technology pollutes.Should be appreciated that in certain embodiments, as required, multiple heat interchanger 610 can be arranged in parallel, to improve the cooling power of component cooling water system 600.If multiple-unit is used, then the maintenance work of arbitrary unit can be performed when reactor operation.

Description above and accompanying drawing represent some example system, should be appreciated that under the spirit not departing from appended claim, scope and suitable ambit, can carry out various increase, amendment and replacement.Especially, those skilled in the art are clear that, when not departing from its spirit or essential characteristic, the present invention can implement with other forms, structure, layout, ratio, size and other components, material and facility.In addition, a lot of method/process described herein can change.Those skilled in the art will be further understood that, when not departing from principle of the present invention, use in the improvement of the present invention by many structures, layout, ratio, size, material and parts, or, in enforcement of the present invention, use when being particularly suitable for concrete environment and operation requirements.Therefore, current disclosed embodiment should be considered to illustrative and nonrestrictive, the scope of the present invention limited by appended claim and its equivalents in all cases, but not is limited by aforesaid instructions or embodiment.And appended claim should be construed broadly, not depart from the scope of the present invention and under suitable ambit to be included in, other change and the embodiments of the present invention that can be made by those skilled in the art.

Claims

1. a nuclear power plant components cooling water system, wherein said system comprises:

Limit the containment of the enclosure space be configured to for holding nuclear reactor;

Around the containment enclosed construction of described containment;

Be formed at the annular cistern between described containment and described containment enclosed construction, described annular cistern is configured to provide heating radiator for the heat energy that dissipates; With

Have the exposed heat conduction tube bank in the water being immersed in described annular cistern without shell heat interchanger;

Component cooling water wherein from described nuclear power station flows through described tube bank and is cooled by transferring heat to described annular cistern.

2. system according to claim 1, wherein said tube bank is made up of multiple heat pipe.

3. system according to claim 1 and 2, wherein said tube bank is U-shaped.

4. the system according to any one of claim 1-3, the bottom of wherein said tube bank and the bottom vertical ground of described annular cistern separate.

5. the system according to any one of claim 1-4, wherein said tube bank is vertical orientated.

6. system according to claim 5, wherein said tube bank is connected to the tube sheet by channel support, and described passage defines equal fluid and is connected to the input room of described tube bank and exports room.

7. system according to claim 6, wherein:

Described passage is structurally supported and is limited in described annular cistern, and

Described tube bank is hung from described passage and is expanded in length without restrictions under thermal expansion situation and shorten.

8. system according to claim 1, wherein said component cooling water flows through the cooling water pipeline ring in described nuclear power station, described cooling water pipeline ring is fluidly connected to described heat interchanger, described component cooling water be transported to described heat interchanger and transport described component cooling water from described heat interchanger.

9. system according to claim 8, heating and the component cooling water cooled between the equipment of wherein said cooling water pipeline ring recycle in described annular cistern and described nuclear power station.

10. system according to claim 9, wherein also comprises at least one pump, and described pump is fluidly connected to described cooling water pipeline ring, for driving arrangement chilled water by described cooling water pipeline ring.

11. systems according to claim 8, wherein said cooling water pipeline ring is fluidly connected to passage, and described passage is formed and limits input room and export room on described heat interchanger.

12. systems according to claim 11, the pipeline of wherein said tube bank all has the one end being fluidly connected to described input room and the second end being fluidly connected to described output room.

13. systems according to claim 12, wherein also comprise the dividing plate be arranged in described passage, and described channel partition is become described input room and described output room by described dividing plate.

14. systems according to claim 1, wherein also comprise: discharge spray thrower, and it is arranged on the described exposed tube bank below in described annular cistern, and described spray thrower configures and be arranged as discharge water by described tube bank for cooling.

15. systems according to claim 14, wherein said spray thrower forms the part being provided with the recirculating system of pump being fluidly connected to described annular cistern, and described recirculating system configures and is operable as from described annular reservoir pumping and by described spray thrower, water turned back to described annular cistern.

16. systems according to claim 1, wherein also comprise multiple fin radial substantially, from described containment outwardly and be arranged in described annular cistern, described heat interchanger is arranged in gulf to described fin, and described gulf is formed between the fin adjoined that separates in described annular cistern.

17. systems according to claim 16, the relatively described containment of wherein said fin is tilted alignment.

18. systems according to claim 1, wherein said heat interchanger is arranged at a position in described annular cistern, near the entrance from cistern make-up water supply system, water is drained into described annular cistern by described cistern make-up water supply system, thus compensates the water lost due to evaporation.

19. systems according to claim 14 and 16, the described entrance wherein from described cistern make-up water supply system and spray thrower is positioned at identical gulf.

20. 1 kinds of nuclear power plant components cooling water systems, wherein said system comprises:

Around the containment enclosed construction of described containment;

The annular cistern formed between described containment and described containment enclosed construction, described annular cistern is configured to provide heating radiator for the heat that dissipates;

Have that the exposed heat conduction that is made up of the multiple pipes be immersed in the water of described annular cistern restrains without shell heat interchanger; With

Be arranged on the discharge spray thrower of the described exposed tube bank below in described annular cistern, described spray thrower configures and is arranged as and from annular cistern, discharges recirculation water by described tube bank, for cooling duct;

Component cooling water from described nuclear power station flows through the pipeline of described tube bank and is cooled by transferring heat to described annular cistern.

21. systems according to claim 20, wherein said spray thrower forms the part being provided with the recirculating system of pump being fluidly connected to described annular cistern, and described recirculating system configures and is operable as from described annular reservoir pumping and by described spray thrower, water turned back to described annular cistern.

22. systems according to claim 20, wherein also comprise multiple fin radial substantially, described fin from described containment to described containment enclosed construction outwardly and be arranged in described annular cistern, described heat interchanger and spray thrower are arranged in gulf, and described gulf is formed between the fin adjoined that separates in described annular cistern.

23. systems according to claim 20, wherein said tube bank is U-shaped.

24. systems according to claim 20, the bottom of wherein said tube bank and the bottom vertical ground of described annular cistern separate.

25. systems according to claim 20, wherein said tube bank is vertical orientated.

26. systems according to claim 20, wherein said tube bank is connected to the tube sheet by channel support, and described passage defines equal fluid and is connected to the input room of described tube bank and exports room.

27. systems according to claim 26, wherein:

28. systems according to claim 26, the Guan Jun of wherein said tube bank has the one end being fluidly connected to described input room and the second end being fluidly connected to described output room.

29. systems according to claim 20, wherein said component cooling water flows through the cooling water pipeline ring being provided with pump in described nuclear power station, described cooling water pipeline ring is fluidly connected to described heat interchanger, for described component cooling water being transported to described heat interchanger and transporting described component cooling water from described heat interchanger.

30. 1 kinds of nuclear power plant components cooling water systems, wherein said system comprises:

Limit the containment being configured to the enclosure space holding nuclear reactor;

Around the containment enclosed construction of described containment;

The annular cistern formed between described containment and described containment enclosed construction, described annular cistern is configured to provide heating radiator for the heat energy that dissipates;

From described containment to described containment enclosed construction outwardly and be arranged in described annular cistern be multiplely substantially radial fins, described heat interchanger is arranged in the gulf that circumference extends, and described gulf to be formed in described annular cistern between the adjacent fins to separate for a pair;

Component cooling water wherein from described nuclear power station flows through the pipeline of described tube bank and is cooled by transferring heat to described annular cistern.

31. systems according to claim 30, wherein also comprise:

Be provided with the cistern recirculation conduit system of pump, there is the discharge spray thrower in the described gulf of the described exposed tube bank below be arranged in described annular cistern,

Wherein said cistern recirculation conduit system configuration sends the water pump of extraction to described tube bank cooling duct with being operable as from described annular reservoir pumping with by described discharge spray thrower.

32. systems according to claim 30, wherein also comprise piping system, and the discharge of cistern make-up water is entered the described gulf holding described heat interchanger by it, thus compensates the water lost due to evaporation.

33. systems according to claim 30, the pipeline of wherein said tube bank all has the one end being fluidly connected to the input room be formed in described heat interchanger and the second end being fluidly connected to the output room be formed in described heat interchanger.

34. systems according to claim 33, wherein said input room and described output room are provided in the passage supporting tube sheet adjacent one another are, and described input room and described output room are by being arranged on the dividing plate fluid isolation each other in described passage.

35. systems according to claim 34, wherein each pipeline has the first pipe end, and it is connected to a part for the described tube sheet be connected with described input room fluid; With the second pipe end, it is connected to a part for the described tube sheet be connected with described output room fluid.

36. systems according to claim 35, wherein said first and second pipe ends are linked together by U-shaped pipe bend fluid.

37. systems according to claim 35, wherein said tube bank is U-shaped.

38. systems according to claim 30, wherein said tube bank is vertical orientated.

39. according to system according to claim 38, and wherein said tube bank is hung downwards from the tube sheet being attached to passage, and described passage limits the inlet nozzle of described heat interchanger and the outlet nozzle of described heat interchanger.

40. systems according to claim 30, wherein said component cooling water flows through the cooling water pipeline ring being provided with pump in described nuclear power station, described cooling water pipeline ring is fluidly connected to described heat interchanger, for described component cooling water being transported to described heat interchanger and transporting described component cooling water from described heat interchanger.