KR930018597A - 핵연료 제조방법 - Google Patents

핵연료 제조방법 Download PDF

Info

Publication number
KR930018597A
KR930018597A KR1019930002049A KR930002049A KR930018597A KR 930018597 A KR930018597 A KR 930018597A KR 1019930002049 A KR1019930002049 A KR 1019930002049A KR 930002049 A KR930002049 A KR 930002049A KR 930018597 A KR930018597 A KR 930018597A
Authority
KR
South Korea
Prior art keywords
plutonium
nuclear fuel
oxide
solution
mixture
Prior art date
Application number
KR1019930002049A
Other languages
English (en)
Other versions
KR100290631B1 (ko
Inventor
와인 헤스케드 케신
콜린 헥스터 브리안
Original Assignee
데렉 제임스 맥코맥
브리티쉬 누클레이 퓨엘스 피엘씨
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 데렉 제임스 맥코맥, 브리티쉬 누클레이 퓨엘스 피엘씨 filed Critical 데렉 제임스 맥코맥
Publication of KR930018597A publication Critical patent/KR930018597A/ko
Application granted granted Critical
Publication of KR100290631B1 publication Critical patent/KR100290631B1/ko

Links

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
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/623—Oxide fuels
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors
    • Y10S376/901—Fuel

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

플루토늄-함유 혼합된 핵연료 제조방법을 발표한다. 이 방법은 플루토늄-함유 용액을 선택하고 용액의 플루토늄 동위체 조성물을 결정하고, 용액에서 입상형 플루토늄 산화물을 침전시키고 산화 플루토늄과 입상형 산화 우라늄으로된 혼합물을 제조하고 또한 혼합물로부터 핵연료 압분체를 형성하는 것으로 이루어진다. 혼합물속의 플루토늄의 양은 주어진 식에 따라 조절한다.

Description

핵연료 제조방법
본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음

Claims (5)

  1. 플루토늄 함유 혼합형 산화를 핵연료 제조방법을 먼저 플루토늄-함유 용액을 선택하고 용액의 플루토늄동위체 조성물을 결정하고 용액에서 입상형 산화플루토늄을 침전시키고 산화플루토늄과 또한 입상형 산화우라늄으로된 혼합물을 형성하고 또한 혼합물로부터 핵연료 압분체(compacts)를 만드는 것으로 구성되며 혼합물속의 플루토늄의 양은 다음의 식에 따라 조절하는 것을 특징으로 하는 : △cPu/CPu-α8△f238-α9△f239+α0△f240-α1△f241+a2△f242-[(1-cPu]/c|Pu]α5△f235+αAm△fAm여기서 f238, f239, f240, f241과 f242는 각각 Pu238, Pu239, Pu240, Pu241과 Pu242동위체 성분의 절대 섭동이며 f235는 U235의 절대섭동이고 fAm은 Am241의 절대선동이며 모든값의 양수인 α값은 각 동위원소의 변화에 대한 평균 반응도의 편도함수에 관계한 인자이다.
  2. 제1항에 있어서, 가압형 수반응기용 핵연료의 α값에 있어서, α8 1.5, α9 2.0, α0 1.0, α1 2.0, α2 3.0,,[(1-CPu)/CPu]α5 30.0 and αAm 3.0 인 것을 특징으로 하는 핵연료 제조방법.
  3. 제1항 또는 제2항에 있어서, 산화우라늄이 이산화 우라늄인 것을 특징으로 하는 핵연료 제조방법.
  4. 전술한 모든 항중 한항에 있어서, 압분체는 워통형 펠릿인 것을 특징으로 하는 핵연료 제조방법.
  5. 전술한 어느 항에 따른 제조방법에 따라 제조한 플루토늄 함유 혼합산화물 핵연료.
    ※ 참고사항 : 최초출원 내용에 의하여 공개하는 것임.
KR1019930002049A 1992-02-13 1993-02-15 핵연료 제조방법 KR100290631B1 (ko)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB9203090.7 1992-02-13
GB929203090A GB9203090D0 (en) 1992-02-13 1992-02-13 The production of nuclear fuel

Publications (2)

Publication Number Publication Date
KR930018597A true KR930018597A (ko) 1993-09-22
KR100290631B1 KR100290631B1 (ko) 2001-06-01

Family

ID=10710343

Family Applications (1)

Application Number Title Priority Date Filing Date
KR1019930002049A KR100290631B1 (ko) 1992-02-13 1993-02-15 핵연료 제조방법

Country Status (7)

Country Link
US (1) US5315624A (ko)
EP (1) EP0556027B1 (ko)
JP (1) JPH0611589A (ko)
KR (1) KR100290631B1 (ko)
DE (1) DE69314195T2 (ko)
ES (1) ES2107618T3 (ko)
GB (1) GB9203090D0 (ko)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU95103479A (ru) 1994-03-11 1996-12-27 Уолкер Эссет Мэнеджмент Лимитед Партнершип (US) Игровая система, игровой компьютер, способ проведения игры, лотереи с участием игрока
US7666470B1 (en) 2003-10-24 2010-02-23 Areva Np Inc. Process for manufacturing enhanced thermal conductivity oxide nuclear fuel and the nuclear fuel

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2004256B (en) * 1977-09-16 1982-01-20 Alkem Gmbh Process for the production of uo2/puo2 nuclear fuels
US4261934A (en) * 1978-11-30 1981-04-14 Electric Power Research Institute, Inc. Method for homogenizing mixed oxide nuclear fuels
GB2098787B (en) * 1981-05-19 1985-09-18 British Nuclear Fuels Ltd Production of pellets for nuclear fuel elements
US5089210A (en) * 1990-03-12 1992-02-18 General Electric Company Mox fuel assembly design

Also Published As

Publication number Publication date
EP0556027A3 (en) 1993-11-03
JPH0611589A (ja) 1994-01-21
GB9203090D0 (en) 1992-04-15
KR100290631B1 (ko) 2001-06-01
US5315624A (en) 1994-05-24
EP0556027B1 (en) 1997-10-01
EP0556027A2 (en) 1993-08-18
ES2107618T3 (es) 1997-12-01
DE69314195D1 (de) 1997-11-06
DE69314195T2 (de) 1998-01-29

Similar Documents

Publication Publication Date Title
RU2001118450A (ru) Топливная сборка из запально-воспроизводящих модулей для ядерного реактора (варианты)
JPS5984184A (ja) 沸騰水型原子炉用燃料集合体
GB1148478A (en) Process for manufacturing sintered pellets of nuclear fuel
US4020131A (en) Preparation of mixed oxide nuclear fuel
ES473401A1 (es) Procedimiento para la fabricacimon de materiales combusti- bles nucleares de puo2-uo2.
GB1461263A (en) Ceramic nuclear fuel pellets
US3362882A (en) Fast breeder nuclear reactor
KR850006759A (ko) 핵연료 펠렛트 제조방법
GB1062247A (en) Long lifetime nuclear reactor
GB1461264A (ko)
KR930018597A (ko) 핵연료 제조방법
GB1061274A (en) Improvements in nuclear reactors and a method of operating same
GB1208433A (en) Manufacture of ceramic artefacts having pores
US3140234A (en) Fast reactor core
GB1034505A (en) Improvements in or relating to sintered uranium-plutonium compounds
JPS6228437B2 (ko)
JP2981580B2 (ja) 核燃料体の製造方法
GB1228317A (ko)
GB1320792A (en) Method of manufacturing sintered non-stoichiometric oxides
GB1393101A (en) Ceramic nuclear fuel
SE8501630L (sv) Sett att tillverka sintrade kernbrenslekroppar
JPS52153095A (en) Core structure in boiling water type reactor
JPS54162086A (en) Reactor
GB858991A (en) Improvements relating to nuclear fuel elements
US2852461A (en) Neutronic reactor

Legal Events

Date Code Title Description
A201 Request for examination
E902 Notification of reason for refusal
E701 Decision to grant or registration of patent right
GRNT Written decision to grant
LAPS Lapse due to unpaid annual fee