KR101503266B1 - 중성자 흡수체 및 냉각재를 포함한 하이브리드 히트파이프에 의한 원자력 발전소 설비 냉각용 잔열제거 시스템 - Google Patents
중성자 흡수체 및 냉각재를 포함한 하이브리드 히트파이프에 의한 원자력 발전소 설비 냉각용 잔열제거 시스템 Download PDFInfo
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- KR101503266B1 KR101503266B1 KR1020130084657A KR20130084657A KR101503266B1 KR 101503266 B1 KR101503266 B1 KR 101503266B1 KR 1020130084657 A KR1020130084657 A KR 1020130084657A KR 20130084657 A KR20130084657 A KR 20130084657A KR 101503266 B1 KR101503266 B1 KR 101503266B1
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- 239000006096 absorbing agent Substances 0.000 title description 9
- 239000002826 coolant Substances 0.000 title description 9
- 238000001816 cooling Methods 0.000 claims abstract description 46
- 238000003780 insertion Methods 0.000 claims abstract description 26
- 230000037431 insertion Effects 0.000 claims abstract description 26
- 239000000498 cooling water Substances 0.000 claims description 20
- 239000012530 fluid Substances 0.000 claims description 14
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 10
- 239000000463 material Substances 0.000 claims description 8
- 229910001182 Mo alloy Inorganic materials 0.000 claims description 7
- 229910001055 inconels 600 Inorganic materials 0.000 claims description 6
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 claims description 5
- 229910052744 lithium Inorganic materials 0.000 claims description 5
- QSHDDOUJBYECFT-UHFFFAOYSA-N mercury Chemical compound [Hg] QSHDDOUJBYECFT-UHFFFAOYSA-N 0.000 claims description 5
- 229910052753 mercury Inorganic materials 0.000 claims description 5
- 239000003507 refrigerant Substances 0.000 claims description 5
- 229920000049 Carbon (fiber) Polymers 0.000 claims description 4
- 239000004917 carbon fiber Substances 0.000 claims description 4
- 239000010949 copper Substances 0.000 claims description 4
- VNWKTOKETHGBQD-UHFFFAOYSA-N methane Chemical compound C VNWKTOKETHGBQD-UHFFFAOYSA-N 0.000 claims description 4
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 claims description 3
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims description 3
- 229910052802 copper Inorganic materials 0.000 claims description 3
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 claims description 3
- 238000000034 method Methods 0.000 claims 5
- 239000000446 fuel Substances 0.000 description 29
- 239000003758 nuclear fuel Substances 0.000 description 15
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000005452 bending Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000002915 spent fuel radioactive waste Substances 0.000 description 2
- 229910052580 B4C Inorganic materials 0.000 description 1
- 230000008030 elimination Effects 0.000 description 1
- 238000003379 elimination reaction Methods 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 239000011796 hollow space material Substances 0.000 description 1
- 229910001026 inconel Inorganic materials 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 230000037303 wrinkles Effects 0.000 description 1
Images
Classifications
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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
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- 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
- G21C15/24—Promoting flow of the coolant
- G21C15/257—Promoting flow of the coolant using heat-pipes
-
- 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
- G21C15/24—Promoting flow of the coolant
- G21C15/26—Promoting flow of the coolant by convection, e.g. using chimneys, using divergent channels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/08—Means for heating fuel elements before introduction into the core; Means for heating or cooling fuel elements after removal from the core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/06—Magazines for holding fuel elements or control elements
- G21C19/07—Storage racks; Storage pools
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/10—Construction of control elements
- G21C7/103—Control assemblies containing one or more absorbants as well as other elements, e.g. fuel or moderator elements
-
- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
도 2는 본 발명의 바람직한 제2실시예에 따른 원자력 발전소 설비 냉각용 잔열제거 시스템의 구성을 나타낸 사시도,
도 3은 본 발명의 바람직한 제3실시예에 따른 원자력 발전소 설비 냉각용 잔열제거 시스템의 구성을 나타낸 사시도이다.
12...제어봉 삽입공 30..저장수조
31...냉각수 40...핵연료
110...제1히트파이프 120...승강구동부
130...제2히트파이프 200...단위저장랙
210...히트파이프판 220...핵연료 저장부
230...제3히트파이프 310...제4히트파이프
320...제5히트파이프 330...제6히트파이프
Claims (14)
- 원자로 용기(10)에 배치된 노심(11)의 잔열을 제거하기 위한 원자력 발전소 설비 냉각용 잔열제거 시스템에 있어서,
상기 원자로 용기(10)의 상부에 배치되되, 상기 원자로 용기(10)의 상단에 형성된 삽입공의 위치에 대응되게 상하방향으로 배치되는 제1히트파이프(110);
상기 제1히트파이프(110)의 상부에 체결되어 상기 제1히트파이프(110)를 상하방향으로 승강구동시켜 상기 제1히트파이프(110)를 상기 원자로 용기(10)에 배치된 노심(11)의 제어봉 삽입공(12)에 선택적으로 삽입시키는 승강구동부(120); 및
상기 원자로 용기(10)의 하부면에 밀착되도록 체결되어 상기 노심(11)에 발생되는 잔열을 흡수하여 냉각시키는 제2히트파이프(130);를 포함하되,
상기 제2히트파이프(130)는,
플렉시블한 재질로 이루어져 상기 원자로 용기(10)의 하부면(13)의 형상에 따라 절곡되면서 상기 하부면(13)에 밀착체결되는 것을 특징으로 하는 원자력 발전소 설비 냉각용 잔열제거 시스템.
- 제 1항에 있어서,
상기 제2히트파이프(130)는,
일단이 격납건물(20) 상에 배치되는 저장수조(30)에 체결되고 타단은 상기 원자로 용기(10)의 하부면(13)에 장착되어, 상기 저장수조(30)에 저장된 냉각수(31)를 공급받으며, 상기 노심(11)에서 발생되는 잔열을 흡수하여 냉각수(31)로 전달함으로써 냉각시키는 것을 특징으로 하는 원자력 발전소 설비 냉각용 잔열제거 시스템.
- 삭제
- 제 1항 또는 제 2항에 있어서,
상기 제2히트파이프(130)는,
주름관 구조로 구비되어 상기 원자로 용기(10)의 하부면(13)의 형상에 따라 절곡되면서 상기 하부면(13)에 밀착체결되는 것을 특징으로 하는 원자력 발전소 설비 냉각용 잔열제거 시스템.
- 제 1항에 있어서,
상기 제1히트파이프(110) 또는 제2히트파이프(130)의 내부에 순환되는 작동유체는, 물(H2O), 냉매, 수은(mercury), 리튬(Lithium) 또는, FLiBe(LiF-BeF2) 중 어느 하나인 것을 특징으로 하는 원자력 발전소 설비 냉각용 잔열제거 시스템.
- 제 5항에 있어서,
상기 제1히트파이프(110) 또는 제2히트파이프(130)에 배치된 윅(Wick)은, 탄소섬유(Carbon fiber), 구리(Copper), 탄화규소(SiC) 또는, 탄화붕소(B4C) 중 어느 하나의 재질로 이루어진 것을 특징으로 하는 원자력 발전소 설비 냉각용 잔열제거 시스템.
- 제 6항에 있어서,
상기 제1히트파이프(110) 또는 제2히트파이프(130)의 외형을 형성하는 외부용기는, 인코넬(Inconel) 600 또는 몰리브데넘 합금(Molybdenum alloy) 중 어느 하나의 재질로 이루어진 것을 특징으로 하는 원자력 발전소 설비 냉각용 잔열제거 시스템.
- 삭제
- 삭제
- 삭제
- 삭제
- 삭제
- 삭제
- 삭제
Priority Applications (3)
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KR1020130084657A KR101503266B1 (ko) | 2013-07-18 | 2013-07-18 | 중성자 흡수체 및 냉각재를 포함한 하이브리드 히트파이프에 의한 원자력 발전소 설비 냉각용 잔열제거 시스템 |
CN201410342005.2A CN104299656B (zh) | 2013-07-18 | 2014-07-17 | 核电站设备冷却用余热消除系统 |
US14/335,324 US9865365B2 (en) | 2013-07-18 | 2014-07-18 | Decay heat removal system with hybrid heat pipe having coolant and neutron absorber for cooling nuclear power plant |
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KR1020130084657A KR101503266B1 (ko) | 2013-07-18 | 2013-07-18 | 중성자 흡수체 및 냉각재를 포함한 하이브리드 히트파이프에 의한 원자력 발전소 설비 냉각용 잔열제거 시스템 |
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KR20150010122A KR20150010122A (ko) | 2015-01-28 |
KR101503266B1 true KR101503266B1 (ko) | 2015-03-18 |
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US (1) | US9865365B2 (ko) |
KR (1) | KR101503266B1 (ko) |
CN (1) | CN104299656B (ko) |
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DE202014010418U1 (de) * | 2014-03-19 | 2015-09-23 | Areva Gmbh | Kühlelement zum Kühlen der Kühlflüssigkeit in einem Brennelementbecken, zugehöriges System, Brennelementbecken und kerntechnische Anlage |
KR101703710B1 (ko) * | 2015-11-18 | 2017-02-23 | (주)이엔이티 | 히트파이프를 이용한 사용후 핵연료 피동 냉각시스템 |
WO2017125782A1 (en) * | 2016-01-19 | 2017-07-27 | The Secretary, Department Of Atomic Energy | A system, a device and a method for passive decay heat transport |
CN110168666B (zh) | 2016-12-30 | 2023-11-10 | 纽斯高动力有限责任公司 | 控制棒阻尼系统 |
US11355252B2 (en) | 2016-12-30 | 2022-06-07 | Nuscale Power, Llc | Control rod drive mechanism with heat pipe cooling |
EP3563388A2 (en) | 2016-12-30 | 2019-11-06 | NuScale Power, LLC | Control rod drive mechanism (crdm) with remote disconnect mechanism |
CN108511092A (zh) * | 2018-06-14 | 2018-09-07 | 华南理工大学 | 一种核燃料元件与回路并行式冷却热管嵌套的一体化结构 |
CN110634580B (zh) * | 2019-09-26 | 2022-05-13 | 哈尔滨工程大学 | 一种热管型深海应用核反应堆系统 |
CN110957055B (zh) * | 2019-10-09 | 2022-11-25 | 中国核电工程有限公司 | 一种适用于压水堆核电站的分离式柔性热管冷却系统 |
CN110767332B (zh) * | 2019-10-14 | 2022-07-15 | 哈尔滨工程大学 | 一种用于高温热管堆的非能动余热排出系统 |
CA3161203A1 (en) | 2019-12-11 | 2021-06-17 | Christopher KMIEC | Passive heat removal casks and methods of using the same |
US11300359B2 (en) * | 2019-12-30 | 2022-04-12 | Westinghouse Electric Company Llc | Block style heat exchanger for heat pipe reactor |
CN113299413B (zh) * | 2021-05-25 | 2022-03-01 | 中国核动力研究设计院 | 一种堆腔纳米流体非能动注入冷却系统 |
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Publication number | Publication date |
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CN104299656A (zh) | 2015-01-21 |
US9865365B2 (en) | 2018-01-09 |
CN104299656B (zh) | 2017-04-19 |
KR20150010122A (ko) | 2015-01-28 |
US20150023461A1 (en) | 2015-01-22 |
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