CN204596440U - Improve the reactor core assembly that vertical epithermal neutron beam irradiates flux - Google Patents
Improve the reactor core assembly that vertical epithermal neutron beam irradiates flux Download PDFInfo
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- CN204596440U CN204596440U CN201520200373.3U CN201520200373U CN204596440U CN 204596440 U CN204596440 U CN 204596440U CN 201520200373 U CN201520200373 U CN 201520200373U CN 204596440 U CN204596440 U CN 204596440U
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Abstract
The utility model belongs to anticancer nucleic neutron knife technical field, a kind of reactor core assembly improving vertical epithermal neutron beam irradiation flux is specifically disclosed, this assembly comprises transition section part and heap core segment, fuel assembly comprises top grating, lower grid plate, center-control rod, several fuel rods and several depleted uraniums rod, center-control rod is inserted in top grating, lower grid plate intracardiac, several fuel rods, depleted uranium rod be arranged in top grating, lower grid plate several of unequal-interval circumferentially concentrically ringed; Described end beryllium disc thickness is 5cm, water layer thickness 5mm, and the thickness bottom lower shell is 5.2cm.This assembly effectively effectively can increase epithermal neutron input than part, improves the neutron flux exporting reactor core, reduces core power nonuniformity coefficient.
Description
Technical field
The utility model belongs to neutron capture therapy (BNCT) technical field, is specifically related to a kind of reactor core assembly and the method thereof that improve anticancer nucleic neutron knife (Cancericidal Nuclide Neutron Knife) vertical epithermal neutron beam irradiation flux.
Background technology
Nuclear reactor boron neutron capture therapy neutron source can provide the neutron streaming in two kinds of directions, and one is horizontal direction, then is vertical direction.The neutron beam of nuclear reactor neutron source extraction is so far nearly all the bundle device of horizontal direction.Main cause is that core reflector periphery is with larger space and can be used as arranging bundle device, ensures higher incident neutron intensity simultaneously.Arrive affected part to transmit prescribed dose, BNCT needs line to aim at affected part, under setting beam intensity, maintains certain irradiation time, according to psychological analysis, after patient enters exposure cell, have the potential feared state of mind to nuclear radiation, can be on tenterhooks affected part.What gravity center of human body was minimum is horizontal or formula of lying, and now the mood of people can be released slow by nature.Thus vertical beam is that first BNCT pursues, and it can make patient accept irradiation under natural situation, and perpendicular fasciculus can cover all affected parts of whole body limbs, internal organs.
Big-and-middle-sized research reactor because of reactor core large, load weight, supporting construction and in-pile component are all seated in piles the end, and volume is more greatly, and the heap body that load is heavier is all pressed in again in base foundation structure, thus rises and does not arrange a set of vertical irradiation chamber device between clearancen.Few vertical neutron beam is exactly this reason in BNCT nuclear reactor neutron source in the world so far.
Sole exception be the MITR heap of the U.S., its is by every possible means provided with the vertical neutron beam of a set of BNCT, and really provide the illuminate condition of patient's the most comfortable, because it is heavy water reactor, this bundle can only produce thermal neutron, although beam intensity is high reach 5 × 10
9ncm
?2s
?1outlet flux, but the power of heap is 5000kw, can only make superficial part illness and irradiate, force it to furnish a huge amount of money for around reactor core, draw a superthermal horizontal neutron beam again, irradiate as deep tumor.
Even if General reactions heap arranges irradiation seat below reactor core, due to the existence of reactor core bottom coohng agent circulation requisite space and various complex component, it is epithermal neutron spectrum that the neutron spectra exported is difficult to guarantee, also can not find the vertical epithermal neutron beam that a beam intensity meets the demands in the world.
The reactor core of micro-pile structure is little, and load is light, and whole heap body is suspended on the top frame of pond, and the heap end and lower space exist, for perpendicular fasciculus provides potential arrangement space without load-carrying members framework.Reactor core polycrystalline substance is through improvement and design, and the high-energy neutron that can be leaked out by reactor core smoothly imports and irradiates seat, and it is up to standard to draw a beam intensity, the epithermal neutron beam that quality is outstanding.
Source flux will be made in nuclear reactor to increase, and the most direct way improves heap power exactly.As shown in Figure 1, according to the horizontal epithermal neutron beam parameter (3 × 10 of prior art
8ncm
?2s
?1), it be made up to standardly to depend merely on power to reach, and heap power just needs lifting 3.5 times.To establish vertical superthermal bundle up to standard, heap power needs raising more than 10 times.In order to arrange vertical superthermal bundle, the reactor of a design hundreds of kw of power, that is not just micro-heap.Obviously, this is an infeasible approach at all.
Summary of the invention
The purpose of this utility model is that providing a kind of improves the reactor core assembly that vertical epithermal neutron beam irradiates flux, this reactor core assembly effectively can improve high-energy neutron score shared in core-spectrum, thus increase the intensity of releasing reactor core neutron spectra, widen above-thermal neutron share, and ensure not overbated in zone of transition, the above-thermal neutron score input of sufficient intensity is kept to irradiate in seat, the final flux improved from irradiating the vertical superthermal bundle that seat exports.
Realize the technical scheme of the utility model object: a kind of reactor core assembly improving vertical epithermal neutron beam irradiation flux, this assembly comprises transition section part and heap core segment, and transition portion comprises end beryllium dish, water layer, lower shell base plate; Heap core segment comprises beryllium sheet, side beryllium ring, graphite tile part, aluminium watt part, fuel assembly.In lower shell, side is provided with aluminium watt part, in lower shell, opposite side is provided with graphite tile part, end beryllium dish is installed in bottom lower shell, water layer is provided with between end beryllium tray bottom and lower shell base plate, end beryllium dish is provided with fuel assembly, outside fuel assembly, cover has side beryllium ring, fuel assembly top is provided with beryllium sheet, fuel assembly comprises top grating, lower grid plate, center-control rod, several fuel rods and several depleted uraniums rod, center-control rod is inserted in top grating, intracardiac in lower grid plate, several fuel rods, depleted uranium rod is arranged in top grating, several of the unequal-interval of lower grid plate are circumferentially concentrically ringed.
Described end beryllium disc thickness is 5cm, water layer thickness 5mm, and the thickness bottom lower shell is 5.2cm.
The concentric circles of described top grating, the unequal-interval of lower grid plate is 11.
Described fuel rod amounts to 350,
235u abundance is 14%, 1st circle of top grating, lower grid plate is circumferentially evenly arranged 5 fuel rods, 2nd circle is circumferentially evenly arranged 11 fuel rods, 3rd circle is circumferentially evenly arranged 17 fuel rods, 4th circle is circumferentially evenly arranged 23 fuel rods, and the 5th circle is circumferentially evenly arranged 29 fuel rods, and the 6th circle is circumferentially evenly arranged 35 fuel rods, 7th circle is circumferentially evenly arranged 41 fuel rods, and the 8th circle is circumferentially evenly arranged 47 fuel rods.
9th circle of described top grating, lower grid plate circumferentially arranges 8 zirconium pull bars, and these 8 zirconium pull bars and 45 fuel rods are uniformly distributed along the circumference of top grating, lower grid plate.
10th circle of described top grating, lower grid plate circumferentially arranges 12 depleted uranium rods, this circle 12 depleted uranium rods are circumferentially uniformly distributed with the circumference of 51 fuel rods 2 along top grating, lower grid plate, these 12 depleted uranium rods are divided into 4 groups, every 3 is one group, 3 depleted uranium rods often in group are adjacent, and interblock space is respectively 6 fuel rods, 12 fuel rods, 5 fuel rods; Described top grating, the 11th round of lower grid plate circumferentially arrange 23 depleted uranium rods, and this circle 23 depleted uranium rods are circumferentially uniformly distributed with the circumference of 46 fuel rods 2 along top grating, lower grid plate, this circle 23 adjacent layouts of depleted uranium rod circumferentially.
Advantageous Effects of the present utility model is:
(1) reactor core of the present utility model is undermoderated reactor core, adopts
235the fuel rod of U abundance 14%, reduce reactor core H/U ?5 than being 159.8 (prior art is 190), further increase the deficient degree of moderation of reactor core, to harden the average neutron power spectrum of reactor core, high-energy neutron is leaked out more from reactor core, be of value to the flux increasing superthermal bundle, Fig. 6, Fig. 7 are that prototype micro-heap reactor core under normalization logarithmic coordinate (H/U ?5 ratios 238) is schemed with the radial thermal neutron profiles versus of the utility model reactor core, H/U ?5 less antineutron traps more obvious, therefore the antineutron trap effect of the utility model reactor core is better than prior art.
(3) beryllium dish calculates through multivariant thickness optimization at the end of the present utility model, adopt the thickness of 5cm, the beryllium sheet that middle 10cm is thick compared to existing technology, only increase suitable reactor core U loading amount, reduce the stronger Be of moderating power to the loss of above-thermal neutron simultaneously, increase the input of the upper composition of heat, the final flux improving superthermal bundle.
(3) the utility model has abandoned the design of General reactions heap bottom Large Copacity water cavity, only retain and maintain the unimpeded minimum thickness of natural circulation, greatly reduce the loss of high-energy neutron, partially hard neutron spectra is made to be input to irradiation seat smoothly, form efficient epithermal neutron beam, lower shell have employed thickening aluminum soleplate, the neutron of higher-energy (~ 1Mev) is passed through smoothly, ensure that input neutron spectrum is not softened, the activation gamma-rays produced is filtered by cadmium owing to entering irradiation seat, does not affect irradiation beam.
(4) technique effect of above-mentioned (1) (2) (3), makes more than vertical superthermal beam ratio prior art appraisal raising magnitude.As engineering redundant measure, core power of the present utility model is set to 45kw, 1.5 times are brought up to compared to existing technology, add reactor core neutron flux, for the generation reaching the superthermal bundle of high flux reserves suitable leeway, by non-homogeneous circle apart from fuel rod topological design, solve because power improves the power nonuniformity coefficient that brings problem bigger than normal, reactor after hoisting power still has inherent safety, day-to-day operation reactor core thermal parameter meets the demands, and can be stabilized in lower value by coolant temperature negative feedback decline low-power under basis accident.
(5) vertical epithermal neutron beam of the present utility model, through calculating checking, the power of 45kw can produce 1.2 × 10
9ncm
?2s
?1epithermal neutron flux, be so far in the world
the nuclear reactor epithermal neutron beam design that ratio is the highest.
Accompanying drawing explanation
Fig. 1 is the front view of irradiation unit in prior art;
Fig. 2 is a kind of front view improving the reactor core assembly of vertical epithermal neutron beam irradiation flux provided by the utility model;
Fig. 3 is the front view of reactor core in Fig. 2;
Fig. 4 is the vertical view of reactor core in Fig. 2; .
Fig. 5 is the neutron spectrum distribution plan in thermal reactor.
Fig. 6 is a kind of reactor core assembly prototype---radial Thermal neutron flux density distribution plan of micro-heap improving vertical epithermal neutron beam irradiation flux provided by the utility model.
Fig. 7 is a kind of radial neutron/photon flux density distribution plan improving the reactor core assembly of vertical epithermal neutron beam irradiation flux provided by the utility model.
In figure: 1 is center-control rod, and 2 is fuel rod, 3 is depleted uranium rod, 4 is zirconium pull bar, and 5 is top grating, and 6 is lower grid plate, 7 is upper beryllium sheet, and 8 is end beryllium dish, and 9 is side beryllium ring, 10 is graphite tile part, and 11 is aluminium watt part, and 12 is lower shell, 13 is upper beryllium tablet tray, 14. water layers, 12a. cylindrical shell boss, 12b. cylindrical shell through hole, 15 is fuel assembly.
Embodiment
Below in conjunction with drawings and Examples, the utility model is described in further detail.
As shown in Figure 2, in the lower shell 12 of the reactor core assembly of the anticancer middle daughter nuclide cutter of raising provided by the utility model vertical epithermal neutron beam irradiation flux, side is provided with circular arc tabular aluminium watt part 11, in lower shell 12, opposite side is provided with the graphite tile part 10 of circular arc tabular, along the circumferential direction leaves gap between aluminium watt part 11 and graphite tile part 10.Circular cylinder boss 12a bottom lower shell 12 is provided with end beryllium dish 8, and beryllium dish 8 top, the end is provided with fuel assembly 15, and outside fuel assembly 15, cover has side beryllium ring 9, and fuel assembly 15 top is provided with beryllium tablet tray 13, and upper beryllium tablet tray 13 is embedded with beryllium sheet 7.Be provided with one deck water layer 14 bottom end beryllium dish 8 and between lower shell 12, cylindrical shell boss 12a have the cylindrical shell through hole 12b be communicated with water layer 14.End beryllium dish 8 thickness is 5cm, and water layer 14 thickness is 5mm, and the thickness of lower shell 12 base plate is 52mm.
As shown in Figure 2,3, 4, fuel assembly 15 comprises top grating 5, lower grid plate 6, center-control rod 1, fuel rod 2 and depleted uranium rod 3, the bottom of center-control rod 1, fuel rod 2, depleted uranium rod 3 is inserted in the circular hole of lower grid plate 6, the top of center-control rod 1, fuel rod 2, depleted uranium rod 3 is inserted in top grating 5 circular hole, and top grating 5 is run through on center-control rod 1, fuel rod 2, depleted uranium rod 3 tops.
As shown in Figure 4, top grating 5, lower grid plate 6 are circular slab, top grating 5, lower grid plate 6 all have 393 identical circular holes, 393 circular holes be arranged in top grating 5, lower grid plate 6 11 of unequal-interval circumferentially concentrically ringed.From the circumference near top grating 5, lower grid plate 6 center of circle, these 11 concentrically ringed diameters are followed successively by 21.4mm, 40.4mm, 59.9mm, 80.0mm, 100.6mm, 121.7mm, 143.4mm, 165.6mm, 188.3mm, 211.6mm, 235.4mm.Often enclose from the circumference near the center of circle and be evenly distributed with 5 circular holes successively, 11 circular holes, 17 circular holes, 23 circular holes, 29 circular holes, 35 circular holes, 41 circular holes, 47 circular holes, 53 circular hole, 63 circular holes and 69 circular holes, totally 393 circular holes, i.e. totally 393 grid positions.Be inserted with in the circular hole of top grating 5, lower grid plate 6 and contain
235u enrichment be 14% fuel rod 2 amount to 350,1st circle of top grating 5, lower grid plate 6 is circumferentially evenly arranged 5 fuel rods 2,2nd circle is circumferentially evenly arranged 11 fuel rods 2,3rd circle is circumferentially evenly arranged 17 fuel rods 2,4th circle be circumferentially evenly arranged 23 fuel rods the 2,5th circle be circumferentially evenly arranged 29 fuel rods the 2,6th circle be circumferentially evenly arranged 35 fuel rods 2,7th circle is circumferentially evenly arranged 41 fuel rods the 2,8th circle and is circumferentially evenly arranged 47 fuel rods 2.
As shown in Figure 4, be inserted with zirconium pull bar 4 in the circular hole of top grating 5, lower grid plate 6 and amount to 8, zirconium pull bar 4 is positioned at the 9th circle circumferentially, this circle 8 zirconium pull bars 4 circumferentially and 45 fuel rods 2 are uniformly distributed along the circumference of top grating 5, lower grid plate 6, and fuel rod 2 quantity between adjacent two zirconium pull bars 4 is respectively 6,6,5,6,6,5,6,5.Be inserted with in the circular hole of top grating 5, lower grid plate 6
235u enrichment be 0.35% depleted uranium rod 3 amount to 35,10th circle circumferentially arranges 12 depleted uranium rods 3, this circle 12 depleted uranium rods, 3 and 51 fuel rods 2 are circumferentially uniformly distributed along the circumference of top grating 5, lower grid plate 6, these 12 depleted uranium rods 3 are divided into 4 groups, every 3 is one group, 3 depleted uranium rods 3 often in group are adjacent, and interblock space is respectively 6 fuel rods, 12 fuel rods, 5 fuel rods; 11th round circumferentially arranges 23 depleted uranium rods 3, and this circle 23 depleted uranium rods, 3 and 46 fuel rods 2 are circumferentially uniformly distributed along the circumference of top grating 5, lower grid plate 6, and this circle 23 depleted uranium rods 3 are circumferentially adjacently arranged in the 10th circle depleted uranium rod offside.
A kind of fuel assembly 15 improving the reactor core assembly of anticancer nucleic neutron knife vertical epithermal neutron beam irradiation flux provided by the utility model adopts the reactor core display of non-homogeneous circle distance, and core power is 45kw.
A kind of method improving anticancer nucleic neutron knife vertical epithermal neutron beam irradiation flux provided by the utility model, the method comprises the following steps:
Step (1) reduces reactor core H/U-5, promotes core power and the layout determining fuel rod
Cold conditions reactor core H/U-5 atomic ratio can be expressed as:
Wherein, ρ
h2Ofor the cold conditions density of water, S
h2Ofor the reactor core water total area, H is the height of reactor core active region, M
u-5for in reactor core
235the loading amount of U.
Therefore, fuel rod is improved
235u abundance thus improve
235u loading amount, arranges depleted uranium rod and reduces water area, can reduce the H/U-5 atomic ratio to 159.8 of reactor core.
Carry out dry run calculating to 45kw reactor core as shown in Figure 2, at finding pool water within temperature 20 DEG C, 45kw piles Power operation 4 hours, and fuel element wall temperature still lower than its corresponding water saturation temperature, does not have bubble to produce.When heap power ascension is to 55.8kw, the surperficial wall temperature with the fuel element local place at maximum focus place can reach or slightly exceed corresponding chilled water saturation temperature, namely reach about 387K, and saturation temperature is about 380K, may produces bubble at local place.Reactor safety can be ensured under day-to-day operation and basis accident.Therefore, the power of reactor core is as shown in Figure 2 brought up to 45kw.
Due to heap power ascension, fuel loading amount increases, if still fuel rod is evenly distributed in circumferentially equally spaced with prior art reactor core, the maximum nonuniformity coefficient comparatively large (1.209) of reactor core radial direction, if regulate by means of only depleted uranium rod, aluminium follower, boom unit, cannot obviously reduce maximum nonuniformity coefficient, and control rod and safety rod will be caused to be worth not.Therefore, as shown in Figure 4, the fuel assembly 15 in anticancer middle daughter nuclide cutter reactor core assembly provided by the utility model adopts the fuel rod scheme of non-homogeneous circle distance.
Because reactor core is deficient slowing down, when enclosing apart from when increasing, the moderator water in fuel assembly 15 near fuel rod increases, and moderation of neutrons becomes fully, improves the power of local.And evenly enclose in reactor core, radial peak power uneven factor appears at inner lane usually, therefore adopts inner lane spacing little, and the scheme of the unequal-interval that outer turn separation is large can effectively reduce power nonuniformity coefficient.The quantity of each circle fuel rod is as shown in Fig. 4 and following table 1:
The non-homogeneous circle of table 1 is apart from the geometric arrangement of reactor core
Step (2) transformation transition section
The transition section of transformation prior art irradiation unit as shown in Figure 1, namely the bracing frame between end beryllium dish 8 and lower shell 12 is removed, and weaken end beryllium dish 8 thickness, weakening water layer 14 thickness, increase lower shell 12 bottom thickness, until provided by the utility model a kind of reactor core assembly improving anticancer middle daughter nuclide cutter vertical epithermal neutron beam irradiation flux as shown in Figure 2.
Based on the superthermal Shu Tongliang of prior art, its flux, to reach international standards, should be improved about ten times by the superthermal bundle of anticancer middle daughter nuclide cutter CNNK, and this obviously needs fundamentally to solve superthermal Shu Tongliang problem on the low side.Even if CNNK improves power, a large amount of calculating and optimization are done to the material of slow body, arrangement, size, has also been not enough to the difference of ten times making up flux.Investigate root, outlet line is all that neutron obtains by irradiating seat slowing down, so considers that how making more superthermal flux be input to irradiates seat frame body, is only basic lifting shortcut.
During thermal-neutron reactor stable operation, its neutron flux, with the distribution of energy, is divided into 3 sections by increased energy is rough, as Fig. 5, namely slightly narrow from minimum energy, energy gap, composition is the highest, by Maxwell spectrum thermal neutron distribution; Then be that energy is higher, energy gap is quite wide, composition placed in the middle, press
spectrum moderating process in or epithermal neutron distribution (its superthermal composition is about inversely proportional to energy); Thereafter be exactly the fission spectrum that energy is the highest, energy gap is slightly wide and composition is on the low side.Heap as BNCT will be inducted into the composition of this section of epithermal neutron spectrum the surface being mapped to and irradiating seat frame body exactly with lowest loss with maximum possible.
The transition bed (superthermal bundle is positioned at horizontal level) of prior art irradiation unit horizontal direction is as shown in Figure 1 side beryllium ring 9 and aluminium watt part 11, water layer, the lower shell 12 (rear three's thickness about 10cm altogether) of 10cm, and epithermal neutron is exported flux slowing down to 3 × 10 by the transition bed of 20cm
8ncm
-2s
-1below, epithermal neutron beam seat due to the reactor core assembly of the anticancer middle daughter nuclide cutter (CNNK) of one raising provided by the utility model vertical epithermal neutron beam irradiation flux is arranged on the bottom of reactor core, if keep the polycrystalline substance of prior art, namely the end beryllium dish 8 that 10cm is as shown in Figure 1 thick, bottom the layer of diw 14 of 33cm and the Al lower shell 12 of 1.4cm, namely the transition length of 44.4cm will make epithermal neutron flux become lower.Therefore need to compress its transition section.
In Be, H2O, Al, that moderating power is the strongest is Be, the neutron leaking out reactor core first process be exactly Be layer.Be layer stenosis that 10cm the is thick energy gap of superthermal spectrum, again reduces the composition of superthermal spectrum.One deck water layer 14 below end beryllium dish 8, its chilled water act as through reactor core heating is flowed downward from outlet flow by the runner gap between heap container, walk around both sides aluminium watt part 11 and graphite tile part 10 mixes with colder aqueous phase at this place, flow up into reactor core central inlet runner by the draft of Natural Circulation pressure head and form natural circulation cooling.The existence that thickness reaches the water layer 14 of 33cm not only weakens the epithermal neutron releasing reactor core further, simultaneously the fast neutron released also fully slowing down become almost heat energy and cannot utilizing.That bottom constructed of aluminium lower shell 12, its moderating power is more weak below water layer 14, little on high-energy neutron impact.
To sum up consider, the thickness weakening end beryllium dish 8 and water layer 14 effectively can increase epithermal neutron input than part, considers that radiation damage is strengthened, increases lower shell 12 bottom thickness.As shown in Figure 2, weaken as 5cm through optimizing by lower beryllium sheet 8, water layer 14 weakens as 5mm, increases to 52mm bottom lower shell 12, and lower beryllium sheet 8, weakening water layer 14, lower shell 12 bottom thickness amount to 10.7cm.
A kind ofly runnability and the security that the vertical epithermal neutron beam of anticancer middle daughter nuclide cutter irradiates the reactor core assembly of flux is improved in order to provided by the utility model after investigating hoisting power, the coolant flow field utilizing cfdrc FLUENT to analyze reactor core and pile in cylindrical shell, gives Core cooling agent inlet flow rate and the distribution at heap in-core thereof.And utilize COBRA-IV program to carry out Steady State Thermal hydraulic analysis to CNNK reactor core.The thermal-hydraulic parameter of CNNK under 45kw declared working condition is as shown in table 2 below:
The non-homogeneous circle of following table 2 is apart from thermal parameter result of calculation under reactor core display
It is known as calculated that " clad temperature is less than 90 DEG C of known heap in-cores and can not seethes with excitement, and reactor core thermal parameter meets design requirement and has enough margins of safety.In calculating operationally, even if be under the operating mode of 40 DEG C in initial temperature, after 8 hours, the temperature of fuel core body is also far below the limiting design value of 200 DEG C, clad temperature maximal value reaches 106.7 DEG C, and comparatively water saturation temperature 111.4 DEG C is low 4.7 DEG C, close to subcooled boiling occurs.And in the operation setting of actual CNNK, only need Operation at full power three hours every day.There is not the safety problem on thermal technology in therefore daily operation.
For basis accident, adopt RELAP5/SCDAP/MOD3.4 program to calculate the control rod withdrawal accident out of control that CNNK piles up under zero power phase, it is reactive that step introduces 6.7mk, and the introducing time is 0.001s, safety rod attonity.Result of calculation is " reactor capability reduces and is stabilized in lower value under coolant temperature negative feedback, and fuel and clad temperature all remain in safe range, and reactor is safe ".
Flow Field Distribution when running a kind of reactor core assembly improving anticancer middle daughter nuclide cutter vertical epithermal neutron beam irradiation flux provided by the utility model is analyzed, at consideration graphite tile part 10, aluminium watt part 11, when impact, the flow of annular entry is 0.225kg/s, central inlet flow is 0.132kg/s, ring exit flow is 0.357kg/s, wherein central inlet is water and is passed downwardly through 5mm water layer under end beryllium by side, the part flow of reactor core is upwards flowed into again by end beryllium medium pore canal, the flow number of 0.132kg/s demonstrates water layer 14 gap to be cut to 5mm and can't block the Natural Circulation of bottom, reactor still normally can carry out Natural Circulation heat exchange.
In conjunction with the accompanying drawings and embodiments the utility model is explained in detail above, but the utility model is not limited to above-described embodiment, in the ken that those of ordinary skill in the art possess, various change can also be made under the prerequisite not departing from the utility model aim.The content be not described in detail in the utility model all can adopt prior art.
Claims (6)
1. one kind is improved the reactor core assembly that vertical epithermal neutron beam irradiates flux, it is characterized in that: this assembly comprises transition section part and heap core segment, and transition portion comprises end beryllium dish (8), water layer (14), lower shell (12) base plate, heap core segment comprises this assembly and comprises beryllium sheet (7), side beryllium ring (9), graphite tile part (10), aluminium watt part (11), with fuel assembly (15), lower shell (12) interior side is provided with aluminium watt part (11), lower shell (12) interior opposite side is provided with graphite tile part (10), lower shell (12) is provided with end beryllium dish (8) in bottom, water layer (14) is provided with between bottom, end beryllium dish (8) and lower shell (12), be provided with fuel assembly (15) end beryllium dish (8), fuel assembly (15) outside cover has side beryllium ring (9), fuel assembly (15) top is provided with beryllium sheet (7), fuel assembly (15) comprises top grating (5), lower grid plate (6), center-control rod (1), several fuel rods (2) and several depleted uranium rods (3), center-control rod (1) is inserted in top grating (5), intracardiac in lower grid plate (6), several fuel rods (2), depleted uranium rod (3) is arranged in top grating (5), several of the unequal-interval of lower grid plate (6) are circumferentially concentrically ringed.
2. a kind of reactor core assembly improving vertical epithermal neutron beam irradiation flux according to claim 1, it is characterized in that: described lower beryllium sheet (7) thickness is 5cm, water layer (14) thickness 5mm, the thickness of lower shell (12) bottom is 5.2cm.
3. a kind of reactor core assembly improving vertical epithermal neutron beam irradiation flux according to claim 2, is characterized in that: the concentric circles of described top grating (5), the unequal-interval of lower grid plate (6) is 11.
4. a kind of reactor core assembly improving vertical epithermal neutron beam irradiation flux according to claim 3, is characterized in that: described fuel rod (2) amounts to 350,
235u abundance is 14%, 1st circle of top grating (5), lower grid plate (6) is circumferentially evenly arranged 5 fuel rods (2), 2nd circle is circumferentially evenly arranged 11 fuel rods (2), 3rd circle is circumferentially evenly arranged 17 fuel rods (2), 4th circle is circumferentially evenly arranged 23 fuel rods (2), 5th circle is circumferentially evenly arranged 29 fuel rods (2), 6th circle is circumferentially evenly arranged 35 fuel rods (2), 7th circle is circumferentially evenly arranged 41 fuel rods (2), and the 8th circle is circumferentially evenly arranged 47 fuel rods (2).
5. a kind of reactor core assembly improving vertical epithermal neutron beam irradiation flux according to claim 4, it is characterized in that: the 9th circle of described top grating (5), lower grid plate (6) circumferentially arranges 8 zirconium pull bars (4), and these 8 zirconium pull bars (4) are uniformly distributed with the circumference of 45 fuel rods (2) along top grating (5), lower grid plate (6).
6. a kind of reactor core assembly improving vertical epithermal neutron beam irradiation flux according to claim 5, its feature exists: described top grating (5), 10th circle of lower grid plate (6) circumferentially arranges 12 depleted uranium rods (3), this circle 12 depleted uranium rods (3) circumferentially and 51 fuel rods (2) are along top grating (5), the circumference of lower grid plate (6) is uniformly distributed, these 12 depleted uranium rods (3) are divided into 4 groups, every 3 is one group, 3 depleted uranium rods (3) often in group are adjacent, interblock space is respectively 6 fuel rods, 12 fuel rods, 5 fuel rods, described top grating (5), the 11th round of lower grid plate (6) circumferentially arrange 23 lean rods (3), this circle 23 depleted uranium rods (3) are circumferentially uniformly distributed with the circumference of 46 fuel rods (2) along top grating (5), lower grid plate (6), this circle 23 adjacent layouts of depleted uranium rod (3) circumferentially.
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| CN104778987A (en) * | 2015-04-03 | 2015-07-15 | 中国中原对外工程有限公司 | Core assembly and method for increasing irradiation flux of vertical epithermal neutron beams |
| TWI609709B (en) * | 2015-10-29 | 2018-01-01 | 住友重機械工業股份有限公司 | Neutron capture therapy system |
| CN107929958A (en) * | 2018-01-04 | 2018-04-20 | 北京新核医疗科技有限公司 | A kind of MNSR Reactor neutron therapy device |
| CN107967954A (en) * | 2017-11-24 | 2018-04-27 | 北京新核医疗科技有限公司 | Horizontal neutron beam illuminating method, MNSR Reactor neutron therapy device and medical system |
| CN108053910A (en) * | 2017-12-07 | 2018-05-18 | 中国核动力研究设计院 | A kind of solution reactor clean reactor |
| CN113192657A (en) * | 2021-04-29 | 2021-07-30 | 西南科技大学 | Non-uniform control rod with reflecting layer |
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2015
- 2015-04-03 CN CN201520200373.3U patent/CN204596440U/en not_active Withdrawn - After Issue
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104778987A (en) * | 2015-04-03 | 2015-07-15 | 中国中原对外工程有限公司 | Core assembly and method for increasing irradiation flux of vertical epithermal neutron beams |
| CN104778987B (en) * | 2015-04-03 | 2017-12-12 | 中国中原对外工程有限公司 | Improve the reactor core assembly and its method of vertical epithermal neutron beam irradiation flux |
| TWI609709B (en) * | 2015-10-29 | 2018-01-01 | 住友重機械工業股份有限公司 | Neutron capture therapy system |
| CN107967954A (en) * | 2017-11-24 | 2018-04-27 | 北京新核医疗科技有限公司 | Horizontal neutron beam illuminating method, MNSR Reactor neutron therapy device and medical system |
| CN107967954B (en) * | 2017-11-24 | 2023-08-04 | 北京新核核工程科技有限公司 | Horizontal neutron beam irradiation method, micro-reactor neutron treatment device and medical system |
| CN108053910A (en) * | 2017-12-07 | 2018-05-18 | 中国核动力研究设计院 | A kind of solution reactor clean reactor |
| CN107929958A (en) * | 2018-01-04 | 2018-04-20 | 北京新核医疗科技有限公司 | A kind of MNSR Reactor neutron therapy device |
| CN113192657A (en) * | 2021-04-29 | 2021-07-30 | 西南科技大学 | Non-uniform control rod with reflecting layer |
| CN113192657B (en) * | 2021-04-29 | 2022-11-04 | 西南科技大学 | Non-uniform control rod with reflecting layer |
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