Filters
Results 1 - 10 of 3992
Results 1 - 10 of 3992.
Search took: 0.032 seconds
Sort by: date | relevance |
AbstractAbstract
[en] In France the complete closure of the fuel cycle can be reached in 3 steps. The first step relies on the improvement of the present fuel cycle by implementing the use of reprocessed uranium (URT) and by enlarging the use of MOX fuel from 900 MW to 1300 MW PWR. The first loading of URT fuel is planned in 2023. The second step will be the multi-recycling of plutonium. The loading of a test fuel assembly with multi-recycled Pu in a PWR core could be made in 2025-2028 and the industrial deployment may be made in 2040 at the soonest. The third step implies the development of a fleet of fast reactors that will allow a limitless recycling of spent fuels and no necessity of using enriched natural uranium. (A.C.)
Original Title
Fermer le cycle du combustible
Primary Subject
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Tamai, Hiroshi; Mochiji, Toshiro; Senzaki, Masao; Kitade, Yuta
Proceedings of the 41st annual meeting of INMM Japan Chapter2020
Proceedings of the 41st annual meeting of INMM Japan Chapter2020
AbstractAbstract
[en] For the peaceful use of nuclear energy, ensuring nuclear non-proliferation and nuclear security as well as nuclear safety is a key issue. Japan have promoted the peaceful uses of plutonium with the nuclear non-proliferation commitment based on IAEA safeguards agreement and Japan-US nuclear cooperation agreement, as well as ensuring transparency of the policy that Japan has no plutonium without purpose of use. In promoting the nuclear fuel cycle, adherence to those measures and maintaining plutonium utilization by means of plutonium use in LWR, and a fast reactor cycle to achieve large-scale and long-term energy supply and environmental improvement, therefore, further research and development is essential. Based on the knowledge and experience of research and development in the nuclear fuel cycle, nuclear material management, the effective and efficient deployment of new technologies should be promoted with scientific and demonstrative measures to strengthen the world's nuclear non-proliferation and nuclear security. Development or sophistication of new technologies, and human resource development will be future Japan’s contribution to the international community. (author)
Original Title
核燃料サイクルの推進と核不拡散・核セキュリティの確保
Primary Subject
Source
Institute of Nuclear Materials Management, Japan Chapter, Tokyo (Japan); [241 p.]; Nov 2020; 4 p; 41. annual meeting of INMM Japan Chapter. Online; Japan (Japan); 19-20 Nov 2020; Available from Institute of Nuclear Materials Management, Japan Chapter, 2-2-3 Uchisaiwai-Cho, Chiyoda-ku, Tokyo, 100-0011 Japan; Available as a PDF file
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Items discussed included: 1. Co-Chairmen's report on the June 1978 Technical Co-Ordinating Committee. 2. Task 1: Collection of basic data. Task 2: Current methods of Pu storage: Base case. Task 3: Current methods of plutonium transport: Base case. Task 7: Plutonium recycle: Base case. Task 8: Assessment of base case for plutonium recycle. 3. Assessment of base cases. 4. Tasks 4 and 5: Technological alternatives for plutonium storage and transport. 5. Task 9: Plutonium recycle - reactor alternatives. 6. Task 6: Alternative institutional arrangements. 7. Preparation of report on the tasks. 8. Task 11: Plutonium recycle - reprocessing alternatives
Primary Subject
Secondary Subject
Source
Oct 1978; 23 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The items discussed include the assessment of proliferation resistance, safeguards and alternative institutional arrangements
Primary Subject
Secondary Subject
Source
Dec 1978; 15 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Based on the reference case of a mixed oxide fuel fabrication facility this paper defines various improvements or different plutonium fuel concepts which could reduce proliferation risks and yield economy in processing. The paper considers in turn: co-location, co-conversion and co-processing. It concludes that co-location and co-conversion could be successfully applied in the medium term on an industrial scale
Primary Subject
Source
Dec 1978; 4 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A recent Evaluation and Screening (E/S) study of nuclear fuel cycle options was conducted by grouping all potential options into 40 Evaluation Groups (EGs) based on similarities in fundamental physics characteristics and fuel cycle performance. Through a rigorous evaluation process considering benefit and challenge metrics, 4 of these EGs were identified by the E/S study as 'most promising'. All 4 involve continuous recycle of U/Pu or U/TRU with natural uranium feed in fast critical reactors. However, these most promising EGs also include fuel cycle groups with variations on feed materials, neutron spectra, and reactor criticality. Therefore, the impacts of the addition of natural thorium fuel feed to a system that originally only used natural uranium fuel feed, using an intermediate spectrum instead of a fast spectrum, and using externally-driven systems versus critical reactors were evaluated. It was found that adding thorium to the natural uranium feed mixture leads to lower burnup, higher mass flows, and degrades fuel cycle benefit metrics (waste management, resource utilization, etc.) for fuel cycles that continuously recycle U/Pu or U/TRU. Adding thorium results in fissions of 233U instead of just 239Pu and in turn results in a lower average number of neutrons produced per absorption (η) for the fast reactor system. For continuous recycling systems, the lower η results in lower excess reactivity and subsequently lower achievable fuel burnup. This in turn leads to higher mass flows (fabrication, reprocessing, disposal, etc.) to produce a given amount of energy and subsequent lower metrics performance. The investigated fuel cycle options with intermediate spectrum reactors also exhibited degraded performance in the benefit metrics compared to fast spectrum reactors. Similarly, this is due to lower η values as the spectrum softens. The best externally-driven systems exhibited similar performance as fast critical reactors in terms of mass flows, but they face much greater challenges, including higher waste generation and higher economic and development costs associated with the external neutron supply. Therefore, any fuel cycle option within the most promising EGs that include thorium in the feed mixture, involves intermediate spectrum reactors, or uses externally-driven systems will be less promising than the reference fast spectrum critical reactor with only natural uranium feed. (authors)
Primary Subject
Secondary Subject
Source
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France); 3390 p; 2015; p. 2741-2749; ICAPP 2015: Nuclear Innovations for a low-carbon future; Nice (France); 3-6 May 2015; Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France); 10 refs.; This record replaces 48095477
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Items discussed included: 1. Progress reports from the Japanese/British Technical Secretariat, contributing countries and organisations. Task 1: Collection of basic data. Task 2: Current methods of plutonium storage. Task 3: Current methods of plutonium transport. Task 7: Plutonium recycle: Base case. 2. Numbering and distribution of papers
Primary Subject
Secondary Subject
Source
Apr 1978; vp
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Transactions of the American Nuclear Society 1975 annual meeting; New Orleans, LA; 8 Jun 1975; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 21 p. 260-261
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Thomas, W.; Brenig, H.; Haider, G.; Hesse, U.; Mueller, W.; Wurtinger, W.
Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany, F.R.)1982
Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany, F.R.)1982
AbstractAbstract
[en] The amount of plutonium produced is estimated. A survey of fuel cycles employed to date and of the use of plutonium is set up. The existing safety analyses are registered and characterized. Possible fuel cycle alternatives are registered, the state-of-the-art in the various fuel cycle concepts are examined, intervention of third parties and subnational deviation are discussed. (DG)
[de]
Der Anfall von Pu wird abgeschaetzt. Es erfolgt eine Erstellung der Bilanz der bisher praktizierten Brennstoffkreislaeufe und der Pu-Verwendung. Vorliegende sicherheitstechnisch orientierte Analysen werden erfasst und charakterisiert. Die moeglichen Brennstoffkreislaufalternativen sind erfasst und der Entwicklungsstand der einzelnen Brennstoffkreislaufkonzepte ist geprueft, Eingriffsmoeglichkeiten Dritter und subnationale Abzweigung werden behandelt. (DG)Original Title
Sicherheitsstrategie Plutonium-Verwendung
Primary Subject
Source
Sep 1982; vp; CONTRACT BMI SR 232; 82 001; Available from Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany, F.R.)
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Yu Yuxuan; Feng Jilian
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.5--Radiation Protection sub-volume2018
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.5--Radiation Protection sub-volume2018
AbstractAbstract
[en] Based on the engineering situation in China, the essay analyzes the variation of the radioactivity from depleted recycled uranium and compares it with that of natural uranium. Moreover, according to the radiation characters of gamma photons, the external dose rates at specific positions outside a single storage tank and multiple ones in two-tier storage condition are calculated respectively using data base ENSDF. Then the dose rates from depleted recycled uranium are compared with the corresponding values from natural uranium. (authors)
Primary Subject
Source
Chinese Nuclear Society, Beijing (China); 211 p; ISBN 978-7-5022-8776-4;
; Apr 2018; p. 107-111; 2017 academic annual meeting of China Nuclear Society; Weihai (China); 16-18 Oct 2017; 3 figs., 7 tabs., 3 refs.

Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |