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Prototype fast breeder reactor Monju : its history and achievements : translated document (JAEA-technology ; 2019-20)

Prototype fast breeder reactor Monju : its history and achievements : translated document (JAEA-technology ; 2019-20)
紙図書
Tsuruga Comprehensive Research and Development Center, Sector of Fast Reactor and Advanced Reactor Research and Development, Japan Atomic Energy Agency2020.3<M19-D11>
国立国会図書館

International review on safety requirements for the prototype fast breeder reactor "Monju" (JAEA-evaluation ; 2015-13)

International review on safety requirements for the prototype fast breeder reactor "Monju" (JAEA-evaluation ; 2015-13)
紙図書
Monju Project Management and Engineering Center [著]Japan Atomic Energy Agency2016.1<M19-B339>
国立国会図書館

A SAS4A study on the ULOF initiating phase energetics of the fast breeder reactor(FBR)

A SAS4A study on the ULOF initiating phase energetics of the fast breeder reactor(FBR)
紙図書
Japan Nuclear Energy Safety Organization2011.2<NG41-B61>
国立国会図書館

Experience of secondary cooling system modification at prototype fast breeder reactor Monju : translated document (JAEA-review ; 2010-36)

Experience of secondary cooling system modification at prototype fast breeder reactor Monju : translated document (JAEA-review ; 2010-36)
紙図書
(eds. ) Naoyuki Kisohara, Yoshihiko SakamotoJapan Atomic Energy Agency2010.9<M19-B225>
国立国会図書館

Denaturing of plutonium by transmutation of minor actinides in fast breeder reactor

Denaturing of plutonium by transmutation of minor actinides in fast breeder reactor
紙博士論文
Yoshitalia Meiliza [著][Yoshitalia Meiliza][2009]<UT51-2011-K58>
国立国会図書館

Study on self-leveling phenomena during a core disruptive accident in a sodium-cooled fast breeder reactor

Study on self-leveling phenomena during a core disruptive accident in a sodium-cooled fast breeder reactor
紙博士論文
Bin Zhang [著][Bin Zhang][2010]<UT51-2010-P783>
国立国会図書館

Symbiotic system of large fast breeder reactors and small thorium fueled satellite-reactors

Symbiotic system of large fast breeder reactors and small thorium fueled satellite-reactors
紙博士論文
Ismail [著][Ismail][2007]<UT51-2008-M139>
国立国会図書館

Feasibility study on water-cooled breeder and fast breeder reactors with thorium fueled in equilibrium states : 富士ゼロックス小林節太郎記念基金2006年度研究助成論文

Feasibility study on water-cooled breeder and fast breeder reactors with thorium fueled in equilibrium states : 富士ゼロックス小林節太郎記念基金2006年度研究助成論文
紙図書
[by] Sidik Permana, 富士ゼロックス小林節太郎記念基金 編富士ゼロックス小林節太郎記念基金2008.5<D9-B186>
国立国会図書館

Basic studies of convection heat transfer related to passive safety of fast breeder reactors

Basic studies of convection heat transfer related to passive safety of fast breeder reactors
紙デジタル博士論文障害者向け資料あり
竹内右人 [著]<UT51-98-G436>
インターネットで読める国立国会図書館

Investigation of in-vessel thermal stratification characteristics for large scale liquid sodium cooled fast breeder reactors with a general-purpose multi-dimensional code aqua / [Hendro Tjahjono, Toshiharu Muramatsu].

Investigation of in-vessel thermal stratification characteristics for large scale liquid sodium cooled fast breeder reactors with a general-purpose multi-dimensional code aqua / [Hendro Tjahjono, Toshiharu Muramatsu].
紙図書
Japan Nuclear Cycle Development Institute, O-arai Engineering Center2001.<NG41-A49>
国立国会図書館

Modeling and validation for molten materials relocation in degraded core of fast breeder reactors

Modeling and validation for molten materials relocation in degraded core of fast breeder reactors
紙デジタル博士論文障害者向け資料あり
澤田哲生 [著]<UT51-96-S491>
インターネットで読める国立国会図書館

Evaluation for the effects of a ring plate device to eliminate free surface gradients in liquid metal fast breeder reactor vessel using multi-dimensional thermohydraulics computer code.

Evaluation for the effects of a ring plate device to eliminate free surface gradients in liquid metal fast breeder reactor vessel using multi-dimensional thermohydraulics computer code.
紙図書
Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation1997.<NG41-A26>
国立国会図書館

Conceptual design of fast breeder reactors cooled by supercritical steam

Conceptual design of fast breeder reactors cooled by supercritical steam
紙デジタル博士論文障害者向け資料あり
Tatjana, Jevremovic [著]<UT51-95-H66>
インターネットで読める国立国会図書館
  • 目次・記事...2.Steam Cooled Fast Reactors Design Review,...... A LARGE-SIZED FAST BREEDER REACTOR CORES ......L STEAM COOLED FAST BREEDER REACTOR (SCFBR......L WATER COOLED FAST BREEDER REACTOR (SCFBR-D) 5.1.Introdu...

Flow induced vebration in liquid metal fast breeder reactors. (Technical reports series ; no. 297)

Flow induced vebration in liquid metal fast breeder reactors. (Technical reports series ; no. 297)
紙図書
International Atomic Energy Agency1989.<Y530-SER.6-STI/DOC/10/297>
国立国会図書館

Sustainable and safe nuclear fission energy : technology and safety of fast and thermal nuclear reactors (Power systems)

Sustainable and safe nuclear fission energy : technology and safety of fast and thermal nuclear reactors (Power systems)
紙図書
Günter Kessler.Springerc2012.<MC261-B20>
国立国会図書館全国の図書館
  • 内容細目...converters and breeder reactors Uranium enrichment Converter reactors with a thermal......utron spectrum Breeder reactors with a fast neutron spectr......of light water reactors and their fuel......d metal cooled fast breeder reactors (LMFBRs).

Comparison of material property specifications of austenitic steels in fast breeder reactors technology / Y. Vanderborck & E. Van Mulders. (EUR ; 10126)

Comparison of material property specifications of austenitic steels in fast breeder reactors technology / Y. Vanderborck & E. Van Mulders. (EUR ; 10126)
紙図書
Commission of the European Communities1985.<Y576-EUR-10126>
国立国会図書館

Fast breeder reactors, experience and trends; proceedings of an International Symposium on East Breeder Reactors, Experiende and Future Trends organizd by the International Atomic Energy Agency and held in Lyons, 22-26 July 1985. (Proceedings series)

Fast breeder reactors, experience and trends; proceedings of an International Symposium on East Breeder Reactors, Experiende and Future Trends organizd by the International Atomic Energy Agency and held in Lyons, 22-26 July 1985. (Proceedings series)
紙図書
International Atomic Energy Agency1986.<Y530-SER.1-STI/PUB/697>
国立国会図書館

Criticality study for the post accident heat removal (PAHR) problem in liquid metal cooled fast breeder reactors / A. Stajadinovic, et al. (EUR ; 9465)

Criticality study for the post accident heat removal (PAHR) problem in liquid metal cooled fast breeder reactors / A. Stajadinovic, et al. (EUR ; 9465)
紙図書
Commission of the European Communities1985.<Y576-EUR-9465>
国立国会図書館

Compendium of post accident heat removal models for liquid metal cooled fast breeder reactors / B.D. Turland & J. Morgan. (EUR ; 10250)

Compendium of post accident heat removal models for liquid metal cooled fast breeder reactors / B.D. Turland & J. Morgan. (EUR ; 10250)
紙図書
Commission of the European Communities1984.<Y576-EUR-10250>
国立国会図書館

Atomic energy, fast breeder reactor safety research : arrangement between the United States of America and France, signed at Paris and Washington June 7 and 21, 1983 (Treaties and other international acts series ; 10741)

Atomic energy, fast breeder reactor safety research : arrangement between the United States of America and France, signed at Paris and Washington June 7 and 21, 1983 (Treaties and other international acts series ; 10741)
マイクロ図書
1985<YCA-S 9.10:10741>
国立国会図書館
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