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IN SITU OBJECT COUNTING SYSTEM (ISOCSTM) TECHNIQUE: COST-EFFECTIVE TOOL FOR GEOMETRICAL RADIATION EFFICIENCY CALCULATION － ITS VERIFICATION WITH AN EU-152 STANDARD SOURCE MEASUREMENT AND MCNP CALCULATIONS

Proceedings of the International Topical Workshop on Fukushima Decommissioning Research, 2022, Vol.2022, p.1023

2022

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Improvement of the “best representativity” method toward an industrial application

Annals of nuclear energy, 2017-07, Vol.105, p.311-328

2017

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Application of the “best representativity” method to a PWR fuel calculation using the critical experiments at the Toshiba NCA facility

Annals of nuclear energy, 2015-11, Vol.85, p.78-92

2015

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Development of a "best representativity" method for experimental data analysis and an application to the critical experiments at the Toshiba NCA facility

Journal of nuclear science and technology, 2014-05, Vol.51 (5), p.608-625

2014

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Neutronics Analysis of Full MOX BWR Core Simulation Experiments FUBILA

Journal of nuclear science and technology, 2011-03, Vol.48 (3), p.398

2011

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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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Analysis of Reactivity Measurements in Core Physics Experiments on Full-MOX BWR

Journal of nuclear science and technology, 2009-06, Vol.46 (6), p.599

2009

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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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Neutronics Analysis of Full MOX BWR Core Simulation Experiments FUBILA

Journal of nuclear science and technology, 2011-03, Vol.48 (3), p.398-420

2011

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Analysis of Reactivity Measurements in Core Physics Experiments on Full-MOX BWR

Journal of nuclear science and technology, 2009-06, Vol.46 (6), p.599-612

2009

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Analysis of High Moderation Full MOX BWR Core Physics Experiments BASALA

Transactions of the Atomic Energy Society of Japan, 2005/03/25, Vol.4(1), pp.45-65

2005

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Analysis of MISTRAL Experiments with JENDL-3.2

Journal of nuclear science and technology, 2002-08, Vol.39 (sup2), p.1061-1066

2002

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Analysis of MOX Core Physics Experiments MISTRAL

Transactions of the Atomic Energy Society of Japan, 2003/03/25, Vol.2(1), pp.39-54

2003

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Critical Experiments on 10% Enriched Uranyl Nitrate Solution Using A 60-cm-Diameter Cylindrical Core

Nuclear technology, 1997-04, Vol.118 (1), p.69-82

1997

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426. 高減速BWR全MOX燃料炉物理試験BASALAの解析

日本原子力学会和文論文誌, 2005/03/25, Vol.4(1), pp.45-65

2005

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380. MOX燃料炉物理試験MISTRALの解析

日本原子力学会和文論文誌, 2003/03/25, Vol.2(1), pp.39-54

2003

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Burnup Sensitivity Analysis in a Fast Breeder Reactor-Part II: Prediction Accuracy of Burnup Characteristics

Nuclear science and engineering, 1985-09, Vol.91 (1), p.11-33

1985

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Enhancement of cytotoxic T-lymphocyte responses in patients with gastrointestinal malignancies following vaccination with CEA peptide-pulsed dendritic cells

Cancer Immunology, Immunotherapy, 2004-07, Vol.53 (7), p.609-616

2004

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Crystal plasticity analysis of lattice defect generation in ULSI cells

The proceedings of the JSME annual meeting, 2002-09, Vol.2002.2, p.81-82

2002

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IN SITU OBJECT COUNTING SYSTEM (ISOCSTM) TECHNIQUE: COST-EFFECTIVE TOOL FOR GEOMETRICAL RADIATION EFFICIENCY CALCULATION － ITS VERIFICATION WITH AN EU-152 STANDARD SOURCE MEASUREMENT AND MCNP CALCULATIONS

Improvement of the “best representativity” method toward an industrial application

Application of the “best representativity” method to a PWR fuel calculation using the critical experiments at the Toshiba NCA facility

Development of a "best representativity" method for experimental data analysis and an application to the critical experiments at the Toshiba NCA facility

Neutronics Analysis of Full MOX BWR Core Simulation Experiments FUBILA

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

Analysis of Reactivity Measurements in Core Physics Experiments on Full-MOX BWR

Intra-pellet neutron flux distribution measurements in LWR critical lattices

Neutronics Analysis of Full MOX BWR Core Simulation Experiments FUBILA

Analysis of Reactivity Measurements in Core Physics Experiments on Full-MOX BWR

Analysis of High Moderation Full MOX BWR Core Physics Experiments BASALA

Analysis of MISTRAL Experiments with JENDL-3.2

Analysis of MOX Core Physics Experiments MISTRAL

Critical Experiments on 10% Enriched Uranyl Nitrate Solution Using A 60-cm-Diameter Cylindrical Core

426. 高減速BWR全MOX燃料炉物理試験BASALAの解析

380. MOX燃料炉物理試験MISTRALの解析

Burnup Sensitivity Analysis in a Fast Breeder Reactor-Part II: Prediction Accuracy of Burnup Characteristics

Enhancement of cytotoxic T-lymphocyte responses in patients with gastrointestinal malignancies following vaccination with CEA peptide-pulsed dendritic cells

Crystal plasticity analysis of lattice defect generation in ULSI cells

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