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Fission Rate Ratios of FCA-IX Assemblies as Integral Experiment for Assessment of TRU’s Fission Cross Sections

EPJ Web of Conferences, 2016, Vol.111, p.7002

2016

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TRU oxide sample reactivity worths measured in the FCA-IX assemblies with systematically changed neutron energy spectra

Journal of nuclear science and technology, 2024-04, Vol.61 (4), p.478-497

2024

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Development of a calculation system for the estimation of decontamination effects

Journal of nuclear science and technology, 2014-05, Vol.51 (5), p.656-670

2014

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Analyses with latest major nuclear data libraries of the fission rate ratios for several TRU nuclides in the FCA-IX experiments

Journal of nuclear science and technology, 2017-07, Vol.54 (7), p.795-805

2017

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JENDL-4.0 Integral Testing for Fission Systems

Journal of the Korean Physical Society, 2011, 59(23), , pp.1135-1140

2011

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Measurement and Analysis of Reactivity Worth of 237Np Sample in Cores of TCA and FCA

Journal of nuclear science and technology, 2009-06, Vol.46 (6), p.624-640

2009

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Development of partitioning and transmutation system using accelerator driven system (ADS): ADS階層型核変換システムについて

Journal of the Atomic Energy Society of Japan, 2016, Vol.58 (2), p.90-92

2016

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Development of partitioning and transmutation system using accelerator driven system (ADS)

Journal of the Atomic Energy Society of Japan, 2016, Vol.58(2), pp.90-92

2016

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Measurement and Analysis of Reactivity Worth of 237Np Sample in Cores of TCA and FCA

Journal of nuclear science and technology, 2009-06, Vol.46 (6), p.624

2009

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Benchmark models for criticalities of FCA-IX assemblies with systematically changed neutron spectra

Journal of nuclear science and technology, 2016-03, Vol.53 (3), p.406-424

2016

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Measurement and Analysis of 238U Doppler Reactivity Effect in FCA Cores Simulating Light-Water-Moderated MOX Fuel Lattices

Journal of nuclear science and technology, 2007-04, Vol.44 (4), p.537-547

2007

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JENDL-4.0 Benchmarking for Fission Reactor Applications

Journal of nuclear science and technology, 2011-02, Vol.48 (2), p.172

2011

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Experimental Reactor Physics “Past, Present and Future”―Towards Establishment of Safety Basis in Next Generation (6): Status and Outlook of Fast Reactor Physics Experiments in JAEA

Journal of the Atomic Energy Society of Japan, 2011, Vol.53(1), pp.50-55

OKAJIMA, Shigeaki

2011

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Role of AES Japan for Contributing to Social Issues: From 60th Anniversary Symposium

Journal of the Atomic Energy Society of Japan, 2019, Vol.61(12), pp.836-839

2019

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Void reactivity evaluation by modified conversion ratio measurements in LWR critical experiments

Journal of nuclear science and technology, 2015-02, Vol.52 (2), p.282-293

2015

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社会課題への貢献に向けた学会の役割: 2019年秋の大会セッションから

日本原子力学会誌ATOMOΣ, 2019, Vol.61(12), pp.836-839

2019

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Research Activities of Japan Nuclear Data Committee in Fiscal Years of 2003 and 2004

Transactions of the Atomic Energy Society of Japan, 2007, Vol.6(1), pp.85-96

2007

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加速器駆動システム(ADS)導入による核燃料サイクルの展開: ADS階層型核変換システムについて

日本原子力学会誌ATOMOΣ, 2016, Vol.58(2), pp.90-92

2016

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Intra-pellet neutron flux distribution measurements in LWR critical lattices

Journal of nuclear science and technology, 2013-06, Vol.50 (6), p.606-614

2013

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Measurement and Analysis of Reactivity Worth of 241Am Sample in Water-Moderated Low-Enriched UO2 Fuel Lattices at TCA

Journal of nuclear science and technology, 2011-05, Vol.48 (5), p.816

2011

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Measurement and Analysis of Reactivity Worth of 241 Am Sample in Water-Moderated Low-Enriched UO 2 Fuel Lattices at TCA

Journal of nuclear science and technology, 2011-05, Vol.48 (5), p.816-825

2011

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Measurement and Analysis of Reactivity Worth of super(241)Am Sample in Water-Moderated Low-Enriched UO sub(2) Fuel Lattices at TCA

Journal of nuclear science and technology, 2011-01, Vol.48 (5)

2011

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実験炉物理：未来へのメッセージ次世代の安全基盤の確立に向けて: 第6回 JAEAの高速炉体系炉物理実験

日本原子力学会誌ATOMOΣ, 2011, Vol.53(1), pp.50-55

岡嶋, 成晃

2011

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JENDL-4.0 Benchmarking for Fission Reactor Applications

Journal of nuclear science and technology, 2011-02, Vol.48 (2), p.172-187

2011

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Measurement and Analysis of Reactivity Worth of 241Am Sample in Water-Moderated Low-Enriched UO2 Fuel Lattices at TCA

Journal of nuclear science and technology, 2011-05, Vol.48 (5), p.816-825

2011

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Fission Rate Ratios of FCA-IX Assemblies as Integral Experiment for Assessment of TRU’s Fission Cross Sections

TRU oxide sample reactivity worths measured in the FCA-IX assemblies with systematically changed neutron energy spectra

Development of a calculation system for the estimation of decontamination effects

Analyses with latest major nuclear data libraries of the fission rate ratios for several TRU nuclides in the FCA-IX experiments

JENDL-4.0 Integral Testing for Fission Systems

Measurement and Analysis of Reactivity Worth of 237Np Sample in Cores of TCA and FCA

Development of partitioning and transmutation system using accelerator driven system (ADS): ADS階層型核変換システムについて

Development of partitioning and transmutation system using accelerator driven system (ADS)

Measurement and Analysis of Reactivity Worth of 237Np Sample in Cores of TCA and FCA

Benchmark models for criticalities of FCA-IX assemblies with systematically changed neutron spectra

Measurement and Analysis of 238U Doppler Reactivity Effect in FCA Cores Simulating Light-Water-Moderated MOX Fuel Lattices

JENDL-4.0 Benchmarking for Fission Reactor Applications

Experimental Reactor Physics “Past, Present and Future”―Towards Establishment of Safety Basis in Next Generation (6): Status and Outlook of Fast Reactor Physics Experiments in JAEA

Role of AES Japan for Contributing to Social Issues: From 60th Anniversary Symposium

Void reactivity evaluation by modified conversion ratio measurements in LWR critical experiments

社会課題への貢献に向けた学会の役割: 2019年秋の大会セッションから

Research Activities of Japan Nuclear Data Committee in Fiscal Years of 2003 and 2004

加速器駆動システム(ADS)導入による核燃料サイクルの展開: ADS階層型核変換システムについて

Intra-pellet neutron flux distribution measurements in LWR critical lattices

Measurement and Analysis of Reactivity Worth of 241Am Sample in Water-Moderated Low-Enriched UO2 Fuel Lattices at TCA

Measurement and Analysis of Reactivity Worth of 241 Am Sample in Water-Moderated Low-Enriched UO 2 Fuel Lattices at TCA

Measurement and Analysis of Reactivity Worth of super(241)Am Sample in Water-Moderated Low-Enriched UO sub(2) Fuel Lattices at TCA

実験炉物理：未来へのメッセージ次世代の安全基盤の確立に向けて: 第6回 JAEAの高速炉体系炉物理実験

JENDL-4.0 Benchmarking for Fission Reactor Applications

Measurement and Analysis of Reactivity Worth of 241Am Sample in Water-Moderated Low-Enriched UO2 Fuel Lattices at TCA

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