KR100935560B1 - 가압수형 원자로의 연료 집합체 및 연료 집합체의 설계방법 - Google Patents
가압수형 원자로의 연료 집합체 및 연료 집합체의 설계방법 Download PDFInfo
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- KR100935560B1 KR100935560B1 KR1020077019646A KR20077019646A KR100935560B1 KR 100935560 B1 KR100935560 B1 KR 100935560B1 KR 1020077019646 A KR1020077019646 A KR 1020077019646A KR 20077019646 A KR20077019646 A KR 20077019646A KR 100935560 B1 KR100935560 B1 KR 100935560B1
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- fuel
- pellet
- outer diameter
- reactivity
- diameter
- Prior art date
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- 239000000446 fuel Substances 0.000 title claims abstract description 513
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 73
- 238000000034 method Methods 0.000 title claims abstract description 21
- 238000013461 design Methods 0.000 title abstract description 15
- 239000008188 pellet Substances 0.000 claims abstract description 210
- 238000002485 combustion reaction Methods 0.000 claims abstract description 107
- 230000007423 decrease Effects 0.000 claims abstract description 76
- 230000009257 reactivity Effects 0.000 claims abstract description 74
- 238000005253 cladding Methods 0.000 claims abstract description 41
- 229910052770 Uranium Inorganic materials 0.000 claims abstract description 32
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims abstract description 32
- 229910001093 Zr alloy Inorganic materials 0.000 claims abstract description 22
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 claims abstract description 17
- 229910000439 uranium oxide Inorganic materials 0.000 claims abstract description 17
- 230000009467 reduction Effects 0.000 claims abstract description 12
- 238000010791 quenching Methods 0.000 claims 3
- 230000000171 quenching effect Effects 0.000 claims 3
- 239000011295 pitch Substances 0.000 description 41
- 239000008233 hard water Substances 0.000 description 20
- 230000008859 change Effects 0.000 description 10
- 239000000498 cooling water Substances 0.000 description 10
- 230000000712 assembly Effects 0.000 description 8
- 238000000429 assembly Methods 0.000 description 8
- 239000002826 coolant Substances 0.000 description 8
- 238000010586 diagram Methods 0.000 description 6
- 230000003247 decreasing effect Effects 0.000 description 4
- 239000007789 gas Substances 0.000 description 3
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 3
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 3
- 230000008021 deposition Effects 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 238000000605 extraction Methods 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 239000001307 helium Substances 0.000 description 2
- 229910052734 helium Inorganic materials 0.000 description 2
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 2
- 238000010248 power generation Methods 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 229910052778 Plutonium Inorganic materials 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000003638 chemical reducing agent Substances 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000036541 health Effects 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 239000013535 sea water Substances 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
- JFALSRSLKYAFGM-OIOBTWANSA-N uranium-235 Chemical compound [235U] JFALSRSLKYAFGM-OIOBTWANSA-N 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/28—Fuel elements with fissile or breeder material in solid form within a non-active casing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
- G21C3/328—Relative disposition of the elements in the bundle lattice
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
-
- 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
Landscapes
- 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
Description
Claims (10)
- 우라늄 산화물을 소결한 연료 펠릿이 지르코늄 합금제 피복관에 충전되어 연료봉이 형성되고, 이 연료봉이 복수 격자상으로 다발지어져 구성된 가압수형 원자로의 연료 집합체에 있어서, 상기 연료 펠릿의 외경이 증가됨으로써 상기 연료 집합체에 장하된 상기 우라늄의 중량이 증가되고, 상기 우라늄의 중량 증가에 따른 연소도의 저하에 의한 반응도의 증가분이, 상기 연료 펠릿의 외경의 증가에 의한 감속재의 감소가 가져오는 감속 부족으로 인하여 생기는 반응도의 저하분을 상회하는 태경화 이득 영역이 구해지고, 상기 반응도가 상회하는 태경화 이득 영역 내에서 상기 연료 펠릿의 외경이 설정된 것을 특징으로 하는 가압수형 원자로의 연료 집합체.
- 제 1 항에 있어서,상기 반응도가 상회하는 태경화 이득 영역은, 상기 연료 펠릿의 외경의 증가로 인하여 뱃치 연소도가 저하되어도, 그 상대적인 저하분을 상회하여 사이클 연소도를 저하시키는 영역인 것을 특징으로 하는 가압수형 원자로의 연료 집합체.
- 우라늄 산화물을 소결한 연료 펠릿이 지르코늄 합금제 피복관에 충전되어 연료봉이 형성되고, 이 연료봉이 복수 격자상으로 다발지어져 구성된 가압수형 원자로의 연료 집합체에 있어서, 상기 복수의 연료봉이 17×17 의 정방 격자상이고, 연 료봉 피치가 12.6㎜ 로 배열된 경우, 상기 연료 펠릿의 외경을 8.25㎜ 보다 크고, 그리고 8.62㎜ 이하로 설정한 것을 특징으로 하는 가압수형 원자로의 연료 집합체.
- 우라늄 산화물을 소결한 연료 펠릿이 지르코늄 합금제 피복관에 충전되어 연료봉이 형성되고, 이 연료봉이 복수 격자상으로 다발지어져 구성된 가압수형 원자로의 연료 집합체에 있어서, 상기 복수의 연료봉이 15×15 의 정방 격자상이고, 연료봉 피치가 14.3㎜ 로 배열된 경우, 상기 연료 펠릿의 외경을 9.35㎜ 보다 크고, 그리고 10.11㎜ 이하로 설정한 것을 특징으로 하는 가압수형 원자로의 연료 집합체.
- 우라늄 산화물을 소결한 연료 펠릿이 지르코늄 합금제 피복관에 충전되어 연료봉이 형성되고, 이 연료봉이 복수 격자상으로 다발지어져 구성된 가압수형 원자로의 연료 집합체에 있어서, 상기 복수의 연료봉이 14×14 의 정방 격자상이고, 연료봉 피치가 14.1㎜ 로 배열된 경우, 상기 연료 펠릿의 외경을 9.35㎜ 보다 크고, 그리고 9.64㎜ 이하로 설정한 것을 특징으로 하는 가압수형 원자로의 연료 집합체.
- 우라늄 산화물을 소결한 연료 펠릿이 지르코늄 합금제 피복관에 충전되어 연료봉이 형성되고, 이 연료봉이 복수 격자상으로 다발지어져 구성된 가압수형 원자로의 연료 집합체의 설계방법에 있어서, 상기 연료 펠릿의 외경을 증가시킴으로써 상기 연료 집합체에 장하된 상기 우라늄의 중량을 증가시키고, 상기 우라늄의 중량 증가에 따른 연소도의 저하에 의한 반응도의 증가분이, 상기 연료 펠릿의 외경의 증가에 의한 감속재의 감소가 가져오는 감속 부족으로 인하여 생기는 반응도의 저하분을 상회하는 태경화 이득 영역을 구하고, 상기 반응도가 상회하는 태경화 이득 영역 내에서 상기 연료 펠릿의 외경을 설정한 것을 특징으로 하는 연료 집합체의 설계 방법.
- 제 6 항에 있어서,상기 반응도가 상회하는 태경화 이득 영역은, 상기 연료 펠릿의 외경의 증가로 인하여 뱃치 연소도가 저하되어도, 그 상대적인 저하분을 상회하여 사이클 연소도를 저하시키는 영역인 것을 특징으로 하는 연료 집합체의 설계 방법.
- 제 1 항 또는 제 2 항에 있어서,상기 복수의 연료봉이 17×17 의 정방 격자상이고, 연료봉 피치가 12.6㎜ 로 배열된 경우, 상기 연료 펠릿의 외경을 8.25㎜ 보다 크고, 그리고 8.62㎜ 이하로 설정한 것을 특징으로 하는 가압수형 원자로의 연료 집합체.
- 제 1 항 또는 제 2 항에 있어서,상기 복수의 연료봉이 15×15 의 정방 격자상이고, 연료봉 피치가 14.3㎜ 로 배열된 경우, 상기 연료 펠릿의 외경을 9.35㎜ 보다 크고, 그리고 10.11㎜ 이하로 설정한 것을 특징으로 하는 가압수형 원자로의 연료 집합체.
- 제 1 항 또는 제 2 항에 있어서,상기 복수의 연료봉이 14×14 의 정방 격자상이고, 연료봉 피치가 14.1㎜ 로 배열된 경우, 상기 연료 펠릿의 외경을 9.35㎜ 보다 크고, 그리고 9.64㎜ 이하로 설정한 것을 특징으로 하는 가압수형 원자로의 연료 집합체.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JPJP-P-2005-00052759 | 2005-02-28 | ||
JP2005052759A JP4138763B2 (ja) | 2005-02-28 | 2005-02-28 | 加圧水型原子炉の燃料集合体及び燃料集合体の設計方法 |
Publications (2)
Publication Number | Publication Date |
---|---|
KR20070100818A KR20070100818A (ko) | 2007-10-11 |
KR100935560B1 true KR100935560B1 (ko) | 2010-01-07 |
Family
ID=36941005
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
KR1020077019646A Active KR100935560B1 (ko) | 2005-02-28 | 2006-02-17 | 가압수형 원자로의 연료 집합체 및 연료 집합체의 설계방법 |
Country Status (6)
Country | Link |
---|---|
US (1) | US20090034675A1 (ko) |
EP (1) | EP1884957A4 (ko) |
JP (1) | JP4138763B2 (ko) |
KR (1) | KR100935560B1 (ko) |
CN (1) | CN101128885B (ko) |
WO (1) | WO2006092970A1 (ko) |
Families Citing this family (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2953637B1 (fr) | 2009-12-04 | 2012-03-23 | Commissariat Energie Atomique | Crayon de combustible nucleaire et procede de fabrication de pastilles d'un tel crayon |
CN102859606A (zh) | 2010-02-05 | 2013-01-02 | 斯姆尔有限公司 | 具有初级冷却剂的自然循环的核反应堆系统 |
FR2963473B1 (fr) * | 2010-07-27 | 2012-09-07 | Areva Np | Procede de controle des positions des assemblages de combustibles nucleaires a l'interieur d'un coeur de reacteur nucleaire, et ensemble de controle correspondant |
US20130114781A1 (en) * | 2011-11-05 | 2013-05-09 | Francesco Venneri | Fully ceramic microencapsulated replacement fuel assemblies for light water reactors |
KR101349135B1 (ko) | 2012-01-04 | 2014-01-09 | 한전원자력연료 주식회사 | 핵연료봉 제조용 소결체 자동적재장치 |
US9728281B2 (en) | 2012-04-17 | 2017-08-08 | Bwxt Mpower, Inc. | Auxiliary condenser system for decay heat removal in a nuclear reactor |
JP6896561B2 (ja) * | 2016-09-26 | 2021-06-30 | 株式会社東芝 | 軽水炉用燃料集合体、軽水炉炉心、軽水炉用燃料集合体製造方法およびmox燃料集合体製造方法 |
CN108854895A (zh) * | 2018-06-15 | 2018-11-23 | 宋波 | 改进型的水反应装置 |
CN116711025A (zh) * | 2020-12-07 | 2023-09-05 | 西屋电气有限责任公司 | 高能核燃料、燃料组件和换料方法 |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5209898A (en) | 1988-12-12 | 1993-05-11 | Siemens Aktiengesellschaft | Fuel element of a pressurized-water-nuclear reactor and fuel rod |
JPH05273369A (ja) * | 1992-03-25 | 1993-10-22 | Nuclear Fuel Ind Ltd | 燃料棒及び燃料集合体 |
Family Cites Families (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
NL244977A (ko) * | 1958-11-04 | 1900-01-01 | ||
US3088893A (en) * | 1960-08-31 | 1963-05-07 | Gen Electric | Malleable tube-clad article and manufacturing method therefor |
US3519537A (en) * | 1968-02-02 | 1970-07-07 | Westinghouse Electric Corp | Internal gas adsorption means for nuclear fuel element |
US3886037A (en) * | 1973-08-17 | 1975-05-27 | Us Energy | Nuclear fuel pin controlled failure device |
DE3301965C2 (de) * | 1983-01-21 | 1986-12-04 | Kraftwerk Union AG, 4330 Mülheim | Abschirmelement für einen aus Kernbrennstoffelementen und den Abschirmelementen aufgebauten Reaktorkern |
JP3253989B2 (ja) | 1991-11-11 | 2002-02-04 | 株式会社日立製作所 | 燃料集合体および混合酸化物燃料棒 |
JPH11142560A (ja) | 1997-11-05 | 1999-05-28 | Mitsubishi Heavy Ind Ltd | 原子炉用燃料棒 |
JP4320383B2 (ja) * | 1999-01-18 | 2009-08-26 | 三菱重工業株式会社 | 核燃料ペレット、及び同核燃料ペレットを装填した燃料棒 |
RU2177650C2 (ru) * | 2000-01-26 | 2001-12-27 | Открытое акционерное общество "Машиностроительный завод" | Тепловыделяющая сборка водо-водяного энергетического ядерного реактора |
-
2005
- 2005-02-28 JP JP2005052759A patent/JP4138763B2/ja not_active Expired - Lifetime
-
2006
- 2006-02-17 CN CN2006800064026A patent/CN101128885B/zh active Active
- 2006-02-17 KR KR1020077019646A patent/KR100935560B1/ko active Active
- 2006-02-17 WO PCT/JP2006/302876 patent/WO2006092970A1/ja active Application Filing
- 2006-02-17 US US11/817,275 patent/US20090034675A1/en not_active Abandoned
- 2006-02-17 EP EP06714017A patent/EP1884957A4/en not_active Ceased
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5209898A (en) | 1988-12-12 | 1993-05-11 | Siemens Aktiengesellschaft | Fuel element of a pressurized-water-nuclear reactor and fuel rod |
JPH05273369A (ja) * | 1992-03-25 | 1993-10-22 | Nuclear Fuel Ind Ltd | 燃料棒及び燃料集合体 |
Also Published As
Publication number | Publication date |
---|---|
KR20070100818A (ko) | 2007-10-11 |
WO2006092970A1 (ja) | 2006-09-08 |
US20090034675A1 (en) | 2009-02-05 |
JP2006234719A (ja) | 2006-09-07 |
EP1884957A4 (en) | 2010-12-08 |
JP4138763B2 (ja) | 2008-08-27 |
CN101128885A (zh) | 2008-02-20 |
EP1884957A1 (en) | 2008-02-06 |
CN101128885B (zh) | 2010-12-22 |
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