WO2020009309A1 - Dispositif modulaire d'expérimentation sur flux thermique critique par rapport au refroidissement de paroi extérieure de réacteur nucléaire - Google Patents

Dispositif modulaire d'expérimentation sur flux thermique critique par rapport au refroidissement de paroi extérieure de réacteur nucléaire Download PDF

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Publication number
WO2020009309A1
WO2020009309A1 PCT/KR2019/002781 KR2019002781W WO2020009309A1 WO 2020009309 A1 WO2020009309 A1 WO 2020009309A1 KR 2019002781 W KR2019002781 W KR 2019002781W WO 2020009309 A1 WO2020009309 A1 WO 2020009309A1
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WO
WIPO (PCT)
Prior art keywords
hemisphere
test
module
temperature
supply system
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PCT/KR2019/002781
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English (en)
Korean (ko)
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배병환
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한국수력원자력 주식회사
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Publication of WO2020009309A1 publication Critical patent/WO2020009309A1/fr

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C23/00—Adaptations of reactors to facilitate experimentation or irradiation
    • 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to an apparatus for reactor type outer wall cooling critical heat flux experiment.
  • An object of the present invention is a modular heat reactor outer wall cooling critical heat flux experiment apparatus, the experimental body portion; A measurement system for measuring the temperature of the test body; A power supply system for supplying power to the test body; A cooling water supply system for supplying cooling water to the test body part, and the test body part; A nuclear reactor unit including a hemisphere simulating a nuclear reactor; And a heat insulation unit surrounding the hemisphere with a cooling water flow path interposed therebetween, the hemispheres being circumferentially disposed at the center of a horizontal plane of the hemisphere and separated from each other and including a plurality of test modules capable of heating. Is achieved by.
  • the plurality of test modules may have the same shape.
  • the plurality of test modules may form an outer shape of the hemisphere, and each of the test modules may have a flat fan shape with an end portion cut off, and a cross-sectional area thereof may decrease toward the lower portion.
  • the central portion of the hemispheres surrounded by the ends of the plurality of test modules may be empty.
  • the hemisphere further comprises at least one insulation module positioned between the plurality of test modules, wherein the insulation module may be empty or made of an insulation material.
  • the insulation module is made of an insulator material, the test module and the insulation module has the same appearance shape, each made of four, the test module and the insulation module may be alternately arranged.
  • the reactor unit further includes a heating rod, the test module has a heating rod receiving groove is formed, the power supply system may supply power to the heating rod.
  • the reactor unit further includes a temperature probe, the test module is formed with a temperature probe receiving groove, the measurement system can measure the temperature using the temperature probe.
  • the power supply system may stop supplying power to the heating rod inserted into the corresponding test module.
  • the present invention experimentally proves the ability to cool the outer wall of the reactor vessel, even if a serious accident that melts nuclear fuel occurs, it is possible to sufficiently cool the corium, a material in which the fuel is melted, and lock it in the reactor so that the reactor is not damaged. This prevents damage to containment buildings and prevents radiation exposure to the public, which greatly improves the safety of nuclear power plants and prevents major accidents such as Fukushima nuclear power plant in Japan.
  • FIG. 1 is a block diagram of a critical heat flux experiment apparatus according to a first embodiment of the present invention
  • Figure 2 shows a three-dimensional hemisphere in the critical heat flux experiment apparatus according to the first embodiment of the present invention
  • Figure 3 shows a test module in the critical heat flux experiment apparatus according to the first embodiment of the present invention
  • Figure 4 shows a plan view of a three-dimensional hemisphere in the critical heat flux experiment apparatus according to the first embodiment of the present invention
  • Figure 5 shows a plan view of a three-dimensional hemisphere in the critical heat flux experiment apparatus according to a second embodiment of the present invention
  • FIG. 6 shows a test module in a critical heat flux experiment apparatus according to a third embodiment of the present invention
  • Figure 7 shows a three-dimensional hemisphere in the critical heat flux experiment apparatus according to a fourth embodiment of the present invention.
  • the present invention is to recognize the success of reactor vessel outer wall cooling in a critical accident reactor management strategy in a nuclear power plant, and to prove and verify the reactor vessel outer wall cooling capability experimentally.
  • a two-dimensional critical heat flux experiment apparatus which is a conventional experimental apparatus, has been developed one step further.
  • the reactor vessel outer wall cooling strategy which is used as part of the incident response within the reactor, aims to close the accident without external discharge of the core melt.
  • the decay heat generated in the core melt is continuously removed without damaging the reactor vessel.
  • the cooling water is sufficiently supplied between the reactor vessel outer wall and the insulator so that the heat transferred from the core melt to the lower half of the reactor vessel is completely removed from the reactor vessel outer wall, and the critical heat, which is the upper limit of heat removal from the reactor vessel outer wall.
  • the value must be large enough.
  • This reactor's outer wall cooling critical heat flux tester is a three-dimensional experiment that simulates the lower half of the reactor vessel and measures the critical heat flux due to boiling of the natural convection tank during cooling the outer wall of the reactor.
  • the experimental apparatus is manufactured in a modular manner, so that various environments that can occur in an actual nuclear power plant, for example, a complex insulator part such as a narrow passage between a reactor vessel and an insulator or a reactor cavity structure and an interference part, may be used.
  • a complex insulator part such as a narrow passage between a reactor vessel and an insulator or a reactor cavity structure and an interference part, may be used.
  • the speed of the series can be measured accurately.
  • FIG. 1 is a block diagram of a critical heat flux experiment apparatus according to a first embodiment of the present invention
  • Figure 2 shows a three-dimensional hemisphere in the critical heat flux experiment apparatus according to a first embodiment of the present invention
  • Figure 3 shows the test module in the critical heat flux experiment apparatus according to the first embodiment of the present invention
  • Figure 4 shows a plan view of a three-dimensional hemisphere in the critical heat flux experiment apparatus according to the first embodiment of the present invention.
  • Experiment apparatus 1 includes an experiment body 10, the measurement system 20, the power supply system 30 and the cooling supply system (40).
  • the experiment body 10 includes a reactor unit 100 and a heat insulation unit 200, a flow path is formed between the reactor unit 100 and the heat insulation unit 200.
  • the reactor unit 100 includes a three-dimensional hemisphere 101, a heat rod 150, and a temperature probe 160.
  • the hemispherical body 101 is composed of eight test modules 110 as shown in FIG.
  • Each test module 110 as shown in Figure 3, the top surface is a fan-shaped cut end, the width becomes narrower toward the bottom.
  • the test module 110 is disposed in the circumferential direction with respect to the center of the horizontal plane of the three-dimensional hemisphere 101 and is adjacent to each other. In the first embodiment, the central portion of the hemispherical body 101 is empty.
  • the test module 110 is provided with a heat rod accommodating groove 111 and a temperature probe accommodating groove 112.
  • the heat rods 150 are accommodated in the heat rod accommodating grooves 111 and the temperature probes 160 are accommodated in the temperature probe accommodating grooves 112.
  • Each of the test modules 110 may be heated by the heat transfer rods 150 and heated to different temperatures.
  • Each test module 110 may be made of a conductive material, for example, copper.
  • test module 110 is provided in the same form in the first embodiment, but may be different in other embodiments. In addition, the number of test modules 110 is not limited to eight.
  • the heat insulation unit 200 is provided so that the reactor unit 100 may be accommodated through the flow path.
  • the material of the heat insulation unit 200 may be stainless steel, but is not limited thereto.
  • the measurement system 20 is connected to the temperature probe 160 and measures the temperature of the first portion 110 and the second portion 120.
  • the measurement system 20 may be connected to a separate temperature probe to measure the temperature of the outer surface of the hemisphere 101 more precisely, or to measure the temperature and flow rate of the cooling water.
  • the measurement system 20 may measure pressure and the like in addition to the temperature.
  • the power supply system 30 supplies power to the heating rods 150 to bring each test module 110 to a desired temperature.
  • the test module 110 may be separated from each other to have different temperatures for each test module 110.
  • the cooling water supply system 40 supplies the cooling water to the flow path.
  • the cooling water supply system 40 may include a cooling water tank, and may include a facility for condensing the cooling water vaporized during the experiment.
  • the experiment apparatus 1 may further include a separate control unit, a user operation unit, and / or a display unit.
  • the heating rod 150 and the temperature pro part 160 are installed in the hemisphere 101 and are connected to the power supply system 30 and the measurement system 20, respectively.
  • cooling water is supplied and circulated in the flow path through the cooling water supply system 40.
  • the surface temperature, critical heat flux, etc. are measured while raising each test module 110 to a desired temperature.
  • the power supply system 30 may stop supplying power to the heating rod inserted into the corresponding test module.
  • the upper limit of the surface temperature of the heat transfer rod 150 may be set to 990 ° C.
  • each test module 110 can be controlled at different temperatures, so that the critical heat flux of the complex insulation part such as the narrow portion of the reactor vessel and the insulator passage or the reactor cavity structure and the interference portion can be accurately measured. In other words, it is possible to accurately measure the local critical heat flux phenomenon.
  • the hemisphere 101 according to the second embodiment includes four test modules 110 and four thermal insulation modules 120. Each test module 110 and the insulation module 120 has the same appearance and are alternately arranged.
  • the insulation module 120 may be made of a general insulation material. In another embodiment, at least some of the four insulation modules 120 may be formed of empty spaces.
  • the critical heat flux may be more accurately measured for each test module 110 by reducing the influence of the adjacent test module 110.
  • the hemispherical body 101 described above can be variously modified, which will be described with reference to FIGS. 5 to 7.
  • the hemispherical body 101 according to the third embodiment further includes a central insulation module 130 at the center.
  • the central insulation module 130 is in the form of a long extended cylinder.
  • the central insulation module 130 may be made of the same material as the insulation module 120.
  • the upper surface of the test module 110 of the hemisphere 101 according to the fourth embodiment is intact fan shape.
  • the insulation module 120 may be included, and the insulation module 120 may have the same appearance as the test module 110.
  • the hemisphere 101 according to the fifth embodiment further includes a hemisphere insulator 140 surrounding the test module 110.
  • the reactor outer wall cooling three-dimensional critical heat flux experiment apparatus can determine whether the large reactor outer wall cooling capacity sufficiently secures the thermal margin. This can secure the safety of large reactors by experimentally verifying and verifying the outer wall cooling capability of the reactor vessel in the management strategy of a serious accident reactor in a nuclear power plant.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

La présente invention concerne un dispositif modulaire d'expérimentation sur un flux thermique critique par rapport au refroidissement d'une paroi externe de réacteur nucléaire, comprenant : une partie de corps d'expérimentation ; un système de mesure servant à mesurer la température de la partie de corps d'expérimentation ; un système d'alimentation électrique servant à fournir de l'énergie à la partie de corps d'expérimentation ; et un système d'alimentation en liquide de refroidissement servant à fournir un fluide de refroidissement à la partie de corps d'expérimentation, la partie de corps d'expérimentation comprenant : une unité de réacteur nucléaire comprenant un hémisphère qui imite un réacteur nucléaire ; une unité d'isolation servant à englober l'hémisphère par un trajet de flux de liquide de refroidissement entre l'unité de réacteur nucléaire et l'unité d'isolation, l'hémisphère comprenant une pluralité de modules de test chauffables, qui sont agencés dans une direction circonférentielle au centre d'une surface horizontale de l'hémisphère et sont séparés l'un de l'autre.
PCT/KR2019/002781 2018-07-05 2019-03-11 Dispositif modulaire d'expérimentation sur flux thermique critique par rapport au refroidissement de paroi extérieure de réacteur nucléaire WO2020009309A1 (fr)

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KR1020180078364A KR101967582B1 (ko) 2018-07-05 2018-07-05 모듈 타입의 원자로 외벽 냉각 임계열속 실험장치
KR10-2018-0078364 2018-07-05

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112530623A (zh) * 2020-11-13 2021-03-19 岭东核电有限公司 辐照考验件及辐照装置

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JP2015503088A (ja) * 2011-10-28 2015-01-29 インダストリー−アカデミック・コーオペレーション・ファウンデーション，ヨンナム・ユニバーシティＩｎｄｕｓｔｒｙ−Ａｃａｄｅｍｉｃ Ｃｏｏｐｅｒａｔｉｏｎ Ｆｏｕｎｄａｔｉｏｎ，Ｙｅｕｎｇｎａｍ Ｕｎｉｖｅｒｓｉｔｙ 原子炉冷却管理システム
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Publication number Priority date Publication date Assignee Title
CN112530623A (zh) * 2020-11-13 2021-03-19 岭东核电有限公司 辐照考验件及辐照装置
CN112530623B (zh) * 2020-11-13 2022-05-03 岭东核电有限公司 辐照考验件及辐照装置

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