KR100969644B1 - 고연소도 사용후핵연료를 이용한 핵연료 소결체 제조방법 - Google Patents
고연소도 사용후핵연료를 이용한 핵연료 소결체 제조방법 Download PDFInfo
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- KR100969644B1 KR100969644B1 KR1020080034582A KR20080034582A KR100969644B1 KR 100969644 B1 KR100969644 B1 KR 100969644B1 KR 1020080034582 A KR1020080034582 A KR 1020080034582A KR 20080034582 A KR20080034582 A KR 20080034582A KR 100969644 B1 KR100969644 B1 KR 100969644B1
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- fuel
- nuclear fuel
- sintered body
- spent fuel
- temperature
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
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- 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
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
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- 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
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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
- 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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- 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
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
Description
Claims (6)
- 우라늄 산화물로 구성된 사용후핵연료를 이용하여 중수로용 핵연료 소결체를 제조하는 방법에 있어서,산화/환원 공정을 통해 사용후핵연료 분말을 소결 가능한 미세 분말로 변환시키고, 상기 변환된 소결 가능한 미세 분말을 성형시켜 압분체로 성형한 후, 상기 성형된 압분체를 환원성 분위기 하에서 소결시켜 핵연료 소결체를 제조하되,상기 소결 공정은,최종 소결 온도에 이르기 전에 최종 소결 온도보다 낮은 1,200 ~ 1,400℃의 중간 온도에서 1 ~ 10 시간 유지시킨 후, 1,650 ~ 1850℃의 최종 소결 온도까지 재가열하는 과정을 통해 압분체 내에 포함되어 있는 준휘발성 핵분열생성물을 제거함으로써 핵연료 소결체의 소결 밀도를 증가시키는 것을 특징으로 하는 고연소도 사용후핵연료를 이용한 핵연료 소결체 제조방법.
- 제 1항에 있어서,상기 사용후핵연료는,경수로형 원자로에서 35,000 MWD/MTU 이상 연소되어 배출되는 핵연료인 것을 특징으로 하는 고연소도 사용후핵연료를 이용한 핵연료 소결체 제조방법.
- 제 1항에 있어서,상기 산화/환원 공정에서는,공기를 포함한 산화성 분위기에서 450 ~ 550 ℃의 온도로 유지시키는 산화 공정과;암모니아를 포함한 환원성 분위기에서 650 ~ 750 ℃의 온도로 유지시키는 환원 공정;을 반복적으로 수행하는 것을 특징으로 하는 고연소도 사용후핵연료를 이용한 핵연료 소결체 제조방법.
- 삭제
- 제 1항에 있어서,상기 소결 공정은,수소, 암모니아 또는 수소 및 암모니아의 혼합기체를 포함하는 환원성 분위기 하에서 수행되는 것을 특징으로 하는 고연소도 사용후핵연료를 이용한 핵연료 소결체 제조방법.
- 삭제
Priority Applications (1)
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KR1020080034582A KR100969644B1 (ko) | 2008-04-15 | 2008-04-15 | 고연소도 사용후핵연료를 이용한 핵연료 소결체 제조방법 |
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KR1020080034582A KR100969644B1 (ko) | 2008-04-15 | 2008-04-15 | 고연소도 사용후핵연료를 이용한 핵연료 소결체 제조방법 |
Publications (2)
Publication Number | Publication Date |
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KR20090109238A KR20090109238A (ko) | 2009-10-20 |
KR100969644B1 true KR100969644B1 (ko) | 2010-07-14 |
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KR1020080034582A KR100969644B1 (ko) | 2008-04-15 | 2008-04-15 | 고연소도 사용후핵연료를 이용한 핵연료 소결체 제조방법 |
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Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
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US10685753B1 (en) | 2019-05-17 | 2020-06-16 | Metatomic, Inc. | Systems and methods for fast molten salt reactor fuel-salt preparation |
EP3970163A4 (en) | 2019-05-17 | 2023-01-04 | Metatomic, Inc. | SYSTEMS AND PROCESSES FOR PRODUCTION OF FUEL SALTS FOR MOLTEN SALT REACTORS |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0194295A (ja) * | 1987-10-06 | 1989-04-12 | Japan Atom Energy Res Inst | レーザ直接再処理法 |
JPH10206588A (ja) | 1997-01-17 | 1998-08-07 | Toshiba Corp | 使用済燃料再処理方法およびその装置 |
JPH11248880A (ja) * | 1998-03-06 | 1999-09-17 | Mitsubishi Heavy Ind Ltd | 使用済燃料の処理方法 |
JP2004028808A (ja) | 2002-06-26 | 2004-01-29 | Inst Of Research & Innovation | 使用済み燃料の再処理方法 |
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- 2008-04-15 KR KR1020080034582A patent/KR100969644B1/ko active IP Right Grant
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0194295A (ja) * | 1987-10-06 | 1989-04-12 | Japan Atom Energy Res Inst | レーザ直接再処理法 |
JPH10206588A (ja) | 1997-01-17 | 1998-08-07 | Toshiba Corp | 使用済燃料再処理方法およびその装置 |
JPH11248880A (ja) * | 1998-03-06 | 1999-09-17 | Mitsubishi Heavy Ind Ltd | 使用済燃料の処理方法 |
JP2004028808A (ja) | 2002-06-26 | 2004-01-29 | Inst Of Research & Innovation | 使用済み燃料の再処理方法 |
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