CN204760047U - Structural integrity test platform under reactor pressure vessel IVR condition - Google Patents
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- CN204760047U CN204760047U CN201520460031.5U CN201520460031U CN204760047U CN 204760047 U CN204760047 U CN 204760047U CN 201520460031 U CN201520460031 U CN 201520460031U CN 204760047 U CN204760047 U CN 204760047U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The utility model discloses a structural integrity test platform under reactor pressure vessel IVR condition. It includes operating mode analog system, data acquisition analytic system and safety coefficient, sets up water supply unit, steam condensate unit and heating unit on the operating mode analog system, data acquisition system comprises the measurement element of each unit, safety coefficient sets up at operating mode analog system peripherally. The utility model discloses a flow of control cooling unit water and hot pond analogue unit's heating power wait the boiling heat transfer process that realizes simulation reactor pressure vessel, through the ware wall temperature degree of measuring simulation reactor pressure gauge, meet an emergency, pressure comes analysis simulation reactor pressure vessel's heat -transfer character, for the experimental reference model that provides of reactor pressure vessel's boiling heat transfer, this test platform simple structure is compact, can carry out structural integrity assay to the reactor pressure vessel of simulation, can carry out the analysis to the reactor pressure vessel's of pressurized heat -transfer character, wide application range.
Description
Technical field
The utility model belongs to structural intergrity test platform technical field, be specifically related to a kind of precision high, control reliable, test is simple, can structural intergrity test platform under the reactor pressure vessel IVR condition of simulation reaction core pressure vessel multi-state.
Background technology
Be detained (InVectorRetention, abbreviation IVR) in reactor core fused mass heap to refer to: from reactor pressure vessel external refrigeration reactor core, make reactor core melt retention in reactor pressure vessel.This is the very important severe accident relieving measure of nuclear power plant, and reactor pressure vessel is the heart of nuclear power plant, therefore ensures that the structural intergrity of nuclear reactor pressure container is most important.But in actual assumed condition, for ensureing IVR success, must following measures be taked in design: the in good time release of reactor coolant loop; Reactor pressure vessel floods water level elevation more than 29.9m in containment.But more than hypothesis is optimal situation, if reactor coolant loop release not exclusively (namely having certain interior pressure in reactor pressure vessel), so how to ensure IVR success, if release is complete, can so how ensure that waste heat in heap be taken away by the chilled water of reactor pressure vessel outer wall in official hour? again in IVR evaluates, the actual heat flow density of reactor pressure vessel outside wall surface and critical heat flux density must be calculated and both are compared, if actual value has exceeded critical value, then assumed response core pressure vessel had lost efficacy.
Therefore, interior pressure is necessary to study and without the heat transfer characteristic of reactor pressure vessel in interior pressure situation and structural intergrity thereof.
Utility model content
For the above-mentioned problems in the prior art, the purpose of this utility model be to provide a kind of precision high, control reliable, test is simple, can structural intergrity test platform under the reactor pressure vessel IVR condition of simulation reaction core pressure vessel multi-state.
Structural intergrity test platform under described a kind of reactor pressure vessel IVR condition, comprise Simulated System, data acquisition and analysis system and security system three parts, it is characterized in that Simulated System being arranged water supplying unit, steam-condensation unit and heating unit; Data acquisition system (DAS) is made up of the measuring sensor of each unit, signal picker and industrial computer; Security system is arranged on Simulated System periphery, and described data acquisition and analysis system is arranged on each pipeline of Simulated System, gathers the temperature and pressure parameter of each section, arranges heat-insulation layer outside the pipeline of described water supplying unit and steam-condensation unit.
Structural intergrity test platform under described a kind of reactor pressure vessel IVR condition, it is characterized in that described Simulated System comprises cooling water tank and the simulation reaction core pressure vessel in cooling water tank, simulation reaction core pressure vessel is provided with heating unit, this heating unit comprises the interior thermopair being arranged on simulation reaction core pressure vessel inside, heating electrode, heating electrode is connected with high-voltage power supply, also comprise and be arranged on outer thermopair outside simulation reaction core pressure vessel and foil gauge, the top of simulation reaction core pressure vessel is provided with the first tensimeter and the second safety valve, the bottom of cooling water tank connects water supplying unit, the periphery of cooling water tank arranges security system.
Structural intergrity test platform under described a kind of reactor pressure vessel IVR condition, it is characterized in that described water supplying unit comprises cooling tower and water pump, the water side, bottom of cooling tower connects water pump input end by efferent duct, water pump output terminal is connected with flowrate control valve, flowrate control valve output terminal connects cooling water tank, and this efferent duct arranges three-temperature sensor.
Structural intergrity test platform under described a kind of reactor pressure vessel IVR condition, it is characterized in that described security system comprises divider wall and Sha Chi, described divider wall is arranged on cooling water tank periphery, and Sha Chi is arranged on bottom divider wall.
Structural intergrity test platform under described a kind of reactor pressure vessel IVR condition, it is characterized in that steam-condensation unit is arranged on cooling water tank sidewall, steam-condensation unit comprises two-way, the first via is connected with drain valve, condenser and cooling tower successively by efferent duct, efferent duct between drain valve and condenser is provided with the first temperature sensor and the first electromagnetic flowmeter, efferent duct between condenser and cooling tower is provided with flowmeter, and condenser arranges cooling water system; Second tunnel is connected with steam-water separator and cooling tower successively, pipeline between steam-water separator and cooling tower is arranged the second temperature sensor and the second electromagnetic flowmeter, steam-water separator top is connected with first via pipeline, first via steam-condensation unit and the second road steam-condensation unit are arranged on cooling water tank sidewall, and first via steam-condensation unit is positioned at above the second road steam-condensation unit.
Structural intergrity test platform under described a kind of reactor pressure vessel IVR condition, is characterized in that being provided with cavity bottom described cooling tower, for air circulation on cavity, lowers the temperature to the water of cooling tower; Cooling tower side is provided with liquid level gauge, and top is provided with moisturizing operation valve.
Structural intergrity test platform under described a kind of reactor pressure vessel IVR condition, it is characterized in that the water inlet end of described cooling water system steam is provided with cooling water control valve, cooling water control valve is connected with centrifugal pump, and the water side of cooling water system steam connects reflux pipeline water being accessed underdrainage system.
Structural intergrity test platform under described a kind of reactor pressure vessel IVR condition, it is characterized in that cooling water tank inside is provided with overflow weir, outside is provided with the first liquid level gauge, and cooling water tank top is provided with the second tensimeter and the first safety valve.
Structural intergrity test platform under described a kind of reactor pressure vessel IVR condition, it is characterized in that simulation reaction core pressure vessel also connects gas cylinder by pipeline, this pipeline is provided with operation valve, is reached the simulated conditions of the different pressures of simulation reaction core pressure vessel by the switch of operation valve.
Structural intergrity test platform under described a kind of reactor pressure vessel IVR condition, it is characterized in that mock-up reactor pressure vessel bottom is set to dome head, described dome head outside surface longitudinal separation arranges one group of fin, cooling water tank inwall correspondence position arranges one group of support rim, fin is positioned at above support rim, and keep gap between fin and support rim, after dome head expanded by heating, fin is outwards withstood by support rim.
By adopting above-mentioned technology, the beneficial effects of the utility model are as follows:
1) structural intergrity test platform under a kind of reactor pressure vessel IVR condition of the present utility model, simulation reaction core pressure vessel arranges gas cylinder, can according to test needs, the actual condition of adoption rate method simulation reaction core pressure vessel, simulate the heat transfer characteristic test of reactor pressure vessel under can carrying out the different operating mode such as normal pressure or pressurization, test findings can be used for carrying out assessment for structural integrity to simulating reactor pressure vessel;
2) structural intergrity test platform under a kind of reactor pressure vessel IVR condition of the present utility model, employing gas cylinder pressurizes, can test the heat transfer characteristic of the simulation reaction core pressure vessel having interior pressure, obtain the heat transfer characteristic of pressurized simulation reaction core pressure vessel, can be used for carrying out assessment for structural integrity to pressurized pressure vessel;
3) the utility model adopts modular design, easy to operate, is applicable to interior pressure and the pressure vessel without interior pressure, also can be later reactor pressure vessel Experimental Study of Heat Transfer and provide reference model, have higher using value;
4) the utility model is by arranging fin at dome head outer wall, can increase heat interchanging area, increases heat transfer efficiency; Be provided with support rim at fin outer wall, and leave certain gap, increase structural strength and the rigidity of RPV; This apparatus structure is simply compact, and heat transfer efficiency is high, structural strength and rigidity high, the safety and reliability of nuclear power can be increased;
5) the utility model carrys out the real working condition of simulation reaction core pressure vessel by the heating power etc. of the flow and three tunnel fusion pool analogue units that control a road cooling unit water, the heat transfer characteristic of the simulation reaction core pressure vessel having interior pressure is analyzed by the medium temperature of measure analog reactor pressure vessel both sides, pressure vessel wall temperature, strain, pressure, the critical heat flux density of all right calculating simulation reactor pressure vessel wall, thus carry out the structural intergrity of analysis mode reactor pressure vessel.
Accompanying drawing explanation
Fig. 1 is the utility model structural representation;
Fig. 2 is mock-up reactor pressure vessel head of the present utility model and cooling water tank junction structural representation.
In figure: 1-gas cylinder, the outer thermopair of 2-, 3-divider wall, 4-cooling water tank, 401-support rim, 5-overflow weir, 6-first liquid level gauge, 7-simulation reaction core pressure vessel, 701-dome head, 702-fin, 8-operation valve, 9-first safety valve, 10-second safety valve, 11-high-voltage power supply, thermopair in 12-, 13-heating electrode, 14-first tensimeter, 15-second tensimeter, 16-foil gauge, 17-steam-water separator, 18-drain valve, 19-heat-insulation layer, 20-first temperature sensor, 21-first electromagnetic flowmeter, 22-condenser, 23-cooling water control valve, 24-flowmeter, 25-moisturizing operation valve, 26-centrifugal pump, 27-cooling tower, 28-cavity, 29-second liquid level gauge, 30-second electromagnetic flowmeter, 31-second temperature sensor, 32-reflux pipeline, 33-three-temperature sensor, 34-centrifugal pump, 35-flowrate control valve, the husky pond of 36-.
Embodiment
Below in conjunction with Figure of description, the utility model will be further described, but protection domain of the present utility model is not limited in this:
As depicted in figs. 1 and 2, structural intergrity test platform under reactor pressure vessel IVR condition of the present utility model, comprise Simulated System, data acquisition and analysis system and security system three parts, Simulated System is set to the water supplying unit of this system cooling, the steam-condensation unit allowing steam flow out and the heating unit to this system heating; Data acquisition system (DAS) comprises the measuring sensor such as temperature, pressure of design at each unit, and above-mentioned measuring sensor is connected with signal picker and industrial computer; Security system is arranged on Simulated System periphery, described data acquisition and analysis system is arranged on each pipeline of Simulated System, gather the temperature and pressure parameter of each section, heat-insulation layer 19 is set outside the pipeline of described water supplying unit and steam-condensation unit, improve security and the accuracy of test.
As shown in the figure, described Simulated System comprises cooling water tank 4 and the simulation reaction core pressure vessel 7 in cooling water tank 4, simulation reaction core pressure vessel 7 is provided with heating unit, this heating unit comprises the interior thermopair 12 being arranged on simulation reaction core pressure vessel 7 inside, heating electrode 13, heating electrode 13 is connected with high-voltage power supply 11, also comprise and be arranged on outer thermopair 2 outside simulation reaction core pressure vessel 7 and foil gauge 16, the top of simulation reaction core pressure vessel 7 is provided with the first tensimeter 14 and the second safety valve 10, the bottom of cooling water tank 4 connects water supplying unit, the periphery of cooling water tank 4 arranges security system, described water supplying unit comprises cooling tower 27 and water pump 34, the water side, bottom of cooling tower 27 connects water pump 34 input end by efferent duct, water pump 34 output terminal is connected with flowrate control valve 35, and flowrate control valve 35 output terminal connects cooling water tank 4, and this efferent duct arranges three-temperature sensor 33, described security system comprises divider wall 3 and Sha Chi 36, and it is peripheral that described divider wall 3 is arranged on cooling water tank 4, and Sha Chi 36 is arranged on bottom divider wall 3, steam-condensation unit is arranged on cooling water tank 4 sidewall, steam-condensation unit comprises two-way, the first via is connected with drain valve 18, condenser 22 and cooling tower 27 successively by efferent duct, efferent duct between drain valve 18 and condenser 22 is provided with the first temperature sensor 20 and the first electromagnetic flowmeter 21, efferent duct between condenser 22 and cooling tower 27 is provided with flowmeter 24, and condenser 22 arranges cooling water system, second tunnel is connected with steam-water separator 17 and cooling tower 27 successively, pipeline between steam-water separator 17 and cooling tower 27 is arranged the second temperature sensor 31 and the second electromagnetic flowmeter 30, steam-water separator 17 top is connected with first via pipeline, first via steam-condensation unit and the second road steam-condensation unit are arranged on cooling water tank 4 sidewall, and first via steam-condensation unit is positioned at above the second road steam-condensation unit, first via steam-condensation unit is all generally gas, directly cool through refrigeratory 22 after drain valve 18, water is got back to cooling tower 27 and is continued to use, second road steam-condensation unit may comprise vapour-liquid mixed liquor, gas is separated through steam-water separator 17 and flows out from steam-water separator 17 top exit, with aftertreatment again after the steam of first via steam-condensation unit, the water separated is got back to cooling tower 27 and is continued to use.
Be provided with cavity 28 bottom described cooling tower 27, for air circulation on cavity 28, the water of cooling tower 27 lowered the temperature; Cooling tower 27 side is provided with liquid level gauge 29, and top is provided with moisturizing operation valve 25; The water inlet end of cooling water system steam is provided with cooling water control valve 23, and cooling water control valve 23 is connected with centrifugal pump 26, and the water side of cooling water system steam connects the reflux pipeline 32 water being accessed underdrainage system.
In order to improve experimental safe, the utility model is provided with overflow weir 5 in cooling water tank 4 inside, and outside is provided with the first liquid level gauge 6, and cooling water tank 4 top is provided with the second tensimeter 15 and the first safety valve 9.
In order to the state of different operating mode can be met, the utility model also connects gas cylinder 1 by pipeline at simulation reaction core pressure vessel 7, this gas cylinder 1 is nitrogen, and this pipeline is provided with operation valve 8, is reached the simulated conditions of the different pressures of simulation reaction core pressure vessel 7 by the switch of operation valve 8.
As shown in Figure 2, the utility model is set to dome head 701 by bottom end enclosure structure simulation reaction core pressure vessel 7, the cylindrical hole that chilled water enters is provided with bottom cooling water tank 4, chilled water enters in end socket from this cylindrical hole and cools end socket, described dome head 701 outside surface longitudinal separation arranges one group of fin 702, fin 702 cross sectional shape can arrange trapezoidal, the various shape such as triangle or rectangle, with trapezoidal and triangle best results, and fin 702 inquires that dome head 701 is not bonded with each other near low head base section, be convenient to chilled water flow through, cooling water tank 4 inwall correspondence position arranges one group of support rim 401, fin 702 is positioned at above support rim 401, and between fin 702 and support rim 401, keep the gap of 4-6mm, gap is preferably 5mm, this support rim 401 is V-structure, when after dome head 701 expanded by heating, expand outwardly, fin 702 also expands outwardly simultaneously, withstood by support rim 401.
Fin 702 of the present utility model is preferably 6, and support rim 401 is preferably 12, and the upper/lower terminal of every sheet fin 702 and two support rim 401 corresponding matching, by lower support fin 702 on two support rims 401.
Structural intergrity test platform under reactor pressure vessel IVR condition of the present utility model, according to actual needs, the normal pressure Experimental Study of Heat Transfer of simulation reaction core pressure vessel can be carried out and have pressure Experimental Study of Heat Transfer two kinds of different pressures situations, and the pressure size in its pressurization heat transfer also can directly control by adjusting control valve 8, can current pressure be read by the first tensimeter 14, make the pressure in simulation reaction core pressure vessel 7 reach the value of setting according to the duration adjusting control valve 8 of the first tensimeter 14.
1) when this experiment porch carries out simulation reaction core pressure vessel normal pressure Experimental Study of Heat Transfer, namely need to close gas cylinder 1, make the pressure in simulation reaction core pressure vessel identical with atmospheric pressure, carry out conventional test, this operating mode and the reactor pressure vessel that IVR supposes do not have interior pressure consistent.During test, regulate the flow from water pump 34 water inlet in cooling water tank 4 by flowrate control valve 35, three-temperature sensor 33 being set between water pump 34 and flowrate control valve 35, for surveying inflow temperature, ensureing that this water temperature is normal temperature, if temperature is higher than normal temperature, can be undertaken air-cooled by adding air in cavity 28, if temperature is lower than normal temperature, the water yield that centrifugal pump 26 enters condenser 22 can be reduced, reduce heat transfer effect altogether, the water temperature entering cooling tower 27 from condenser 22 is improved, thus ensureing that the water temperature entering water pump 34 maintains normal temperature, the water yield is controlled by flowrate control valve 35, if the water level that the second liquid level gauge 29 records in cooling tower 27 is too low, supplement distilled water by moisturizing operation valve 25, if the water temperature that the second temperature sensor 31 records is less than 100 DEG C, can reduce the flow velocity of water or reduce the height of overflow weir 5 to reduce the reserves of water in cooling water tank 4 by adjust flux operation valve 35, in cooling water tank 4, the reserves of water can be measured by the first liquid level gauge 6, cooling water tank 4 can produce a large amount of steam when heat exchange, pressure now in cooling water tank 4 can be read by the second tensimeter 15, if pressure superelevation, the first safety valve 9 that now cooling water tank 4 top is arranged can be opened to reduce the pressure in cooling water tank 4 automatically, if pressure is lower, then prove experimental safe, the flow of recirculation water and the generation of steam in cooling water tank 4 can be measured respectively by the second electromagnetic flowmeter 30 and the first electromagnetic flowmeter 21, by the voltage swing regulating the high-voltage power supply 11 be connected with heating electrode 13 to come in, the heat etc. in simulation reaction core pressure vessel 7 is made to reach the real working condition (namely providing enough decay heats) of simulation reaction core pressure vessel, come in measure analog reactor pressure vessel 7 by interior thermopair 12 and outer thermopair 2, outside wall temperature, the strain of measure analog reactor pressure vessel 7 is carried out by the foil gauge 16 of simulation reaction core pressure vessel 7 outer wall, according in the simulation reaction core pressure vessel recorded, outside wall temperature carrys out the heat transfer characteristic of analysis mode reactor pressure vessel 7, namely can by the critical heat flux density of following formulae discovery simulation reaction core pressure vessel 7 wall according to the temperature of simulation reaction core pressure vessel 7 outer wall recorded
q cHF, obtain:
Wherein C
boilfor boiling coefficient, table look-up and can calculate,
T
satfor the saturated cooling water temperature of correspondence (normal atmosphere pressure is 100 DEG C),
T
w2for the temperature of simulation reaction core pressure vessel 7 outside wall surface, this parameter is by the temperature T of this test platform more accurate measure analog reactor pressure vessel 7 outside wall surface
w2, thus calculate the critical heat flux density q of simulation reaction core pressure vessel 7 wall
cHF,
By this value and critical heat flux density, (ordinary test measured value is 1.26MW/m again
2) compare.Critical heat flux density
q cHFwith boiling coefficient C
boilcomputing method can list of references: the work such as F.P.lncropera, D.P.DeWitt, Ge Xinshi, Ye Hongyi, heat transfer and mass transfer ultimate principle [M]. Beijing: Chemical Industry Press, 2009.; If the actual heat flow density of simulation reaction core pressure vessel outside wall surface is greater than critical heat flux density value, then assumed response core pressure vessel lost efficacy; If the actual heat flow density of simulation reaction core pressure vessel 7 outside wall surface is less than critical heat flux density value, then assumed response core pressure vessel 7 can not lose efficacy, and namely kept the structural intergrity of simulation reaction core pressure vessel 7.Other measurement parameter is mainly used for the accuracy ensureing that the inside and outside wall temperature of simulation reaction core pressure vessel 7 is measured; The utility model fundamental purpose is the temperature recording simulation reaction core pressure vessel 7 outside wall surface, and the data of other data acquisition system of the utility model are accuracys of the temperature for proving simulation reaction core pressure vessel 7 outside wall surface;
2) this experiment porch carries out simulation reaction core pressure vessel when having an interior pressure Experimental Study of Heat Transfer, namely need to open gas cylinder 1, pressurize to simulation reaction core pressure vessel 7, make the pressure in simulation reaction core pressure vessel 7 identical with the pressure (multiple different pressures can be supposed) of supposition, carry out there is pressure test.The voltage of the flow of water in cooling water tank 4 and heating electrode 13 is regulated to regulate the heat etc. in simulation reaction core pressure vessel 7 to carry out the real working condition (namely providing enough decay heats) of simulation reaction core pressure vessel by flowrate control valve 35, come in measure analog reactor pressure vessel 7 by interior thermopair 12 and outer thermopair 2, outside wall temperature, the strain of measure analog reactor pressure vessel 7 is carried out by the foil gauge 16 of simulation reaction core pressure vessel 7 outer wall, according in the simulation reaction core pressure vessel 7 recorded, outside wall temperature carrys out the heat transfer characteristic of analysis mode reactor pressure vessel 7, namely according to the critical heat flux density (q of the temperature of simulation reaction core pressure vessel 7 outer wall recorded by following formulae discovery simulation reaction core pressure vessel 7 wall
cHF):
，
Wherein C
boilfor boiling coefficient, table look-up and can calculate,
T
satfor the saturated cooling water temperature of correspondence (normal atmosphere pressure is 100 DEG C),
T
w2for the temperature of simulation reaction core pressure vessel 7 outside wall surface,
Wherein seethe with excitement coefficient C
boilbe calculated as follows:
G-acceleration of gravity in formula, m/s
2
the density of-saturation water and saturated vapor, kg/m
3
-surface tension of liquid, N/m
specific heat of water under-normal pressure, J/ (kgK)
-fluid gasification latent heat, J/kg
-empirical constant, the present invention selects 0.013 according to list of references
P
rl the Prandtl number of-saturation water
-fluid kinematic viscosity, Pas;
This parameter is by the temperature T of this test platform more accurate measure analog reactor pressure vessel 7 outside wall surface
w2, thus calculate the critical heat flux density q of simulation reaction core pressure vessel 7 wall
cHFagain this value and critical heat flux density (ordinary test measured value is 1.26MW/m2) are compared, this computing method list of references: F.P.lncropera, the work such as D.P.DeWitt, Ge Xinshi, Ye Hongyi, heat transfer and mass transfer ultimate principle [M]. Beijing: Chemical Industry Press, 2009.P378 formula 10.3; If the actual heat flow density of simulation reaction core pressure vessel outside wall surface is less than critical heat flux density value, then assumed response core pressure vessel lost efficacy; If the actual heat flow density of simulation reaction core pressure vessel outside wall surface has exceeded critical heat flux density value, then assumed response core pressure vessel can not lose efficacy, and namely kept the structural intergrity of simulation reaction core pressure vessel.
Claims (10)
1. structural intergrity test platform under a reactor pressure vessel IVR condition, comprise Simulated System, data acquisition and analysis system and security system three parts, it is characterized in that Simulated System being arranged water supplying unit, steam-condensation unit and heating unit; Data acquisition system (DAS) is made up of the measuring sensor of each unit, signal picker and industrial computer; Security system is arranged on Simulated System periphery, and described data acquisition and analysis system is arranged on each pipeline of Simulated System, gathers the temperature and pressure parameter of each section, arranges heat-insulation layer (19) outside the pipeline of described water supplying unit and steam-condensation unit.
2. structural intergrity test platform under a kind of reactor pressure vessel IVR condition according to claim 1, it is characterized in that described Simulated System comprises cooling water tank (4) and the simulation reaction core pressure vessel (7) in cooling water tank (4), simulation reaction core pressure vessel (7) is provided with heating unit, this heating unit comprises the interior thermopair (12) being arranged on simulation reaction core pressure vessel (7) inside, heating electrode (13), heating electrode (13) is connected with high-voltage power supply (11), also comprise and be arranged on the outer outer thermopair (2) of simulation reaction core pressure vessel (7) and foil gauge (16), the top of simulation reaction core pressure vessel (7) is provided with the first tensimeter (14) and the second safety valve (10), the bottom of cooling water tank (4) connects water supplying unit, the periphery of cooling water tank (4) arranges security system.
3. structural intergrity test platform under a kind of reactor pressure vessel IVR condition according to claim 2, it is characterized in that described water supplying unit comprises cooling tower (27) and water pump (34), the water side, bottom of cooling tower (27) connects water pump (34) input end by efferent duct, water pump (34) output terminal is connected with flowrate control valve (35), flowrate control valve (35) output terminal connects cooling water tank (4), this efferent duct is arranged three-temperature sensor (33).
4. structural intergrity test platform under a kind of reactor pressure vessel IVR condition according to claim 2, it is characterized in that described security system comprises divider wall (3) He Shachi (36), it is peripheral that described divider wall (3) is arranged on cooling water tank (4), and Sha Chi (36) is arranged on divider wall (3) bottom.
5. structural intergrity test platform under a kind of reactor pressure vessel IVR condition according to claim 2, it is characterized in that steam-condensation unit is arranged on cooling water tank (4) sidewall, steam-condensation unit comprises two-way, the first via by efferent duct successively with drain valve (18), condenser (22) is connected with cooling tower (27), efferent duct between drain valve (18) and condenser (22) is provided with the first temperature sensor (20) and the first electromagnetic flowmeter (21), efferent duct between condenser (22) and cooling tower (27) is provided with flowmeter (24), (22) arrange cooling water system with condenser, second tunnel is connected with steam-water separator (17) and cooling tower (27) successively, pipeline between steam-water separator (17) and cooling tower (27) is arranged the second temperature sensor (31) and the second electromagnetic flowmeter (30), steam-water separator (17) top is connected with first via pipeline, first via steam-condensation unit and the second road steam-condensation unit are arranged on cooling water tank (4) sidewall, and first via steam-condensation unit is positioned at above the second road steam-condensation unit.
6. structural intergrity test platform under a kind of reactor pressure vessel IVR condition according to claim 3, it is characterized in that described cooling tower (27) bottom is provided with cavity (28), for air circulation on cavity (28), the water of cooling tower (27) is lowered the temperature; Cooling tower (27) side is provided with liquid level gauge (29), and top is provided with moisturizing operation valve (25).
7. structural intergrity test platform under a kind of reactor pressure vessel IVR condition according to claim 3, it is characterized in that the water inlet end of described cooling water system steam is provided with cooling water control valve (23), cooling water control valve (23) is connected with centrifugal pump (26), and the water side of cooling water system steam connects the reflux pipeline (32) water being accessed underdrainage system.
8. structural intergrity test platform under a kind of reactor pressure vessel IVR condition according to claim 2, it is characterized in that cooling water tank (4) inside is provided with overflow weir (5), outside is provided with the first liquid level gauge (6), and cooling water tank (4) top is provided with the second tensimeter (15) and the first safety valve (9).
9. structural intergrity test platform under a kind of reactor pressure vessel IVR condition according to claim 2, it is characterized in that simulation reaction core pressure vessel (7) also connects gas cylinder (1) by pipeline, this pipeline is provided with operation valve (8), is reached the simulated conditions of the different pressures of simulation reaction core pressure vessel (7) by the switch of operation valve (8).
10. structural intergrity test platform under a kind of reactor pressure vessel IVR condition according to claim 1, it is characterized in that simulation reaction core pressure vessel (7) bottom is set to dome head (701), described dome head (701) outside surface longitudinal separation arranges one group of fin (702), cooling water tank (4) inwall correspondence position arranges one group of support rim (401), fin (702) is positioned at support rim (401) top, and keep gap between fin (702) and support rim (401), after dome head (701) expanded by heating, fin (702) is outwards withstood by support rim (401).
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN104979025A (en) * | 2015-06-30 | 2015-10-14 | 浙江工业大学 | Platform for testing structural integrity of reactor pressure vessel under IVR condition |
| CN105551542A (en) * | 2016-01-29 | 2016-05-04 | 中国原子能科学研究院 | Water-cooling containment simulation device |
| CN106251919A (en) * | 2016-08-24 | 2016-12-21 | 浙江工业大学 | Reactor pressure vessel security test system under major accident operating mode |
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| WO2021128059A1 (en) * | 2019-12-25 | 2021-07-01 | 中广核研究院有限公司 | Test system for simulating rpv heat exchange characteristics of nuclear power plant, and heating and temperature measuring device |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104979025A (en) * | 2015-06-30 | 2015-10-14 | 浙江工业大学 | Platform for testing structural integrity of reactor pressure vessel under IVR condition |
| CN104979025B (en) * | 2015-06-30 | 2017-07-07 | 浙江工业大学 | Structural intergrity test platform under the conditions of a kind of reactor pressure vessel IVR |
| CN105551542A (en) * | 2016-01-29 | 2016-05-04 | 中国原子能科学研究院 | Water-cooling containment simulation device |
| CN106251919A (en) * | 2016-08-24 | 2016-12-21 | 浙江工业大学 | Reactor pressure vessel security test system under major accident operating mode |
| CN106251919B (en) * | 2016-08-24 | 2018-06-01 | 浙江工业大学 | Reactor pressure vessel security test system under major accident operating mode |
| CN110133037A (en) * | 2019-06-12 | 2019-08-16 | 中国核动力研究设计院 | A kind of experimental provision to conduct heat for studying pool boiling under the structure of different heating face |
| CN110133037B (en) * | 2019-06-12 | 2021-11-30 | 中国核动力研究设计院 | Experimental device for be used for studying pool boiling heat transfer under different heating surface structures |
| WO2021128059A1 (en) * | 2019-12-25 | 2021-07-01 | 中广核研究院有限公司 | Test system for simulating rpv heat exchange characteristics of nuclear power plant, and heating and temperature measuring device |
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