KR840003215A - 핵연료 스크랩의 처리 방법 - Google Patents
핵연료 스크랩의 처리 방법 Download PDFInfo
- Publication number
- KR840003215A KR840003215A KR1019830000184A KR830000184A KR840003215A KR 840003215 A KR840003215 A KR 840003215A KR 1019830000184 A KR1019830000184 A KR 1019830000184A KR 830000184 A KR830000184 A KR 830000184A KR 840003215 A KR840003215 A KR 840003215A
- Authority
- KR
- South Korea
- Prior art keywords
- scrap
- nuclear fuel
- gas
- fuel
- processing method
- Prior art date
Links
- 239000003758 nuclear fuel Substances 0.000 title claims 6
- 239000007789 gas Substances 0.000 claims 6
- 238000000034 method Methods 0.000 claims 4
- 239000000446 fuel Substances 0.000 claims 3
- 238000003672 processing method Methods 0.000 claims 3
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims 2
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims 2
- 239000000463 material Substances 0.000 claims 2
- 230000003647 oxidation Effects 0.000 claims 2
- 238000007254 oxidation reaction Methods 0.000 claims 2
- 239000001301 oxygen Substances 0.000 claims 2
- 229910052760 oxygen Inorganic materials 0.000 claims 2
- 229910052757 nitrogen Inorganic materials 0.000 claims 1
- 230000001590 oxidative effect Effects 0.000 claims 1
- 230000002285 radioactive effect Effects 0.000 claims 1
- 238000005245 sintering Methods 0.000 claims 1
Classifications
-
- 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
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
- B01J8/00—Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes
- B01J8/18—Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles
- B01J8/24—Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles according to "fluidised-bed" technique
- B01J8/40—Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles according to "fluidised-bed" technique with fluidised bed subjected to vibrations or pulsations
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/01—Oxides; Hydroxides
- C01G43/025—Uranium dioxide
-
- 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
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
- C01P2006/00—Physical properties of inorganic compounds
- C01P2006/80—Compositional purity
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/22—Devices for withdrawing samples in the gaseous state
-
- 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
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- Organic Chemistry (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- Ceramic Engineering (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Combustion & Propulsion (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Solid Fuels And Fuel-Associated Substances (AREA)
- Processing Of Solid Wastes (AREA)
- Fluidized-Bed Combustion And Resonant Combustion (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Abstract
내용 없음
Description
본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음
본 발명에 대한 장치의 도식적인 측면도.
Claims (7)
- 스크랩이 유동로내로 들어가서 기체와 함께 균일하게 유동화 되는 UO2핵연료 스크랩을 처리하는 방법에 있어서, 유동화된 상태로 사익 스크랩은 400℃ 이하의 온도로 산화 기체내에서 첫번째 산화를 하는 것과 상기 산화된 스크랩은 그 때 소결성을 개선하고 좀 더 큰 표면 방사능을 가진 물질을 형성하기 위해 환원되는 것을 가진 물질을 형성하기 위해 환원되는 것을 특징으로 하는 UO2핵연료 스크랩의 처리 방법.
- 제1항에서, 유동화 기체가 펄스화되는 것을 특징으로 하는 UO2핵연료 스크랩의 처리 방법.
- 제2항에서, 기체의 펄스는 주파수가 약 0.2-2㎐ 이며, 압력은 약 0.5-3 바아이고 온-사이클은 약 0.1-1초이며, 그리고 오프-사이클은 약 0.4-4초인 것을 특징으로 하는 UO2핵연료스크랩의 처리 방법.
- 제1항, 제2항 또는 제3항에서, 스크랩은 기체내로 운반된 산소와 산화되며, 산소의 부분 압력은 온도를 증가하기 위해 증가되고 온도를 감소하기 위해 감소하는 것을 특징으로 하는 UO2핵연료스크랩의 처리 방법.
- 제2항, 제3항 또는 제4항에서, 산화와 환원단계가 적어도 한번 반복되는 것을 특징으로 하는 UO2핵연료 스크랩의 처리 방법.
- 제3항, 4항 또는 5항에서 유동화 기체가 질소를 포함하는 것을 특징으로 하는 UO2핵연료 스크랩의 처리 방법.
- 제4항, 5항 또는 제 6항에서, 스크랩은 약 400-700℃ 에서 환원되는 것을 특징으로 하는 UO2핵연료 스크랩의 처리 방법.※ 참고사항 : 최초출원 내용에 의하여 공개하는 것임.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US34059382A | 1982-01-19 | 1982-01-19 | |
| US3.40593 | 1982-01-19 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| KR840003215A true KR840003215A (ko) | 1984-08-20 |
Family
ID=23334074
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| KR1019830000184A KR840003215A (ko) | 1982-01-19 | 1983-01-19 | 핵연료 스크랩의 처리 방법 |
Country Status (5)
| Country | Link |
|---|---|
| EP (1) | EP0084129B1 (ko) |
| JP (1) | JPS58124998A (ko) |
| KR (1) | KR840003215A (ko) |
| DE (1) | DE3271902D1 (ko) |
| ES (1) | ES8507287A1 (ko) |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0150737B1 (en) * | 1984-01-26 | 1989-10-04 | Westinghouse Electric Corporation | Process for treating nuclear fuel scrap |
| EP0236298B1 (de) * | 1985-09-09 | 1990-01-17 | Günther Förster | Verfahren und vorrichtung zur verbrennung fester und/oder flüssiger materialien |
| FR2599883B1 (fr) * | 1986-06-10 | 1990-08-10 | Franco Belge Fabric Combustibl | Procede de fabrication de pastilles de combustible nucleaire a base d'oxyde d'uranium |
| KR100794071B1 (ko) * | 2006-12-05 | 2008-01-10 | 한국원자력연구원 | 핵연료 소결체의 제조 방법 |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3140151A (en) * | 1959-11-12 | 1964-07-07 | James R Foltz | Method of reprocessing uo2 reactor fuel |
| FR1315822A (fr) * | 1961-12-11 | 1963-01-25 | Commissariat Energie Atomique | Procédé de traitement d'une poudre de bioxyde d'uranium en vue de-la rendre particulièrement apte au frittage et produit obtenu suivant ce procédé |
| US3343926A (en) * | 1966-02-08 | 1967-09-26 | Irving E Knudsen | Oxidation-reduction procedure for particle-size reduction of uo2 |
| US3578419A (en) * | 1967-12-14 | 1971-05-11 | Gen Electric | Scrap nuclear fuel material recovery process |
| SE346048B (ko) * | 1968-02-01 | 1972-06-19 | Nukem Gmbh | |
| DE2004967A1 (de) * | 1969-03-14 | 1970-09-24 | The Babcock & Wilcox Company, New York, N.Y. (V.St.A.) | Verfahren zur Rückgewinnung von Bestandteilen aus Kernbrennstoff-Schrott |
-
1982
- 1982-12-15 DE DE8282111635T patent/DE3271902D1/de not_active Expired
- 1982-12-15 EP EP82111635A patent/EP0084129B1/en not_active Expired
-
1983
- 1983-01-18 ES ES519079A patent/ES8507287A1/es not_active Expired
- 1983-01-19 KR KR1019830000184A patent/KR840003215A/ko not_active Application Discontinuation
- 1983-01-19 JP JP58005968A patent/JPS58124998A/ja active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| ES519079A0 (es) | 1985-08-16 |
| EP0084129B1 (en) | 1986-07-02 |
| EP0084129A3 (en) | 1983-12-14 |
| ES8507287A1 (es) | 1985-08-16 |
| EP0084129A2 (en) | 1983-07-27 |
| JPH0322600B2 (ko) | 1991-03-27 |
| JPS58124998A (ja) | 1983-07-25 |
| DE3271902D1 (en) | 1986-08-07 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A201 | Request for examination | ||
| E902 | Notification of reason for refusal | ||
| E601 | Decision to refuse application |