須山 賢也

Study on the specifications of the basic core configurations of the modified STACY 

Annals of Nuclear Energy 209 2024年12月15日  

Neutronics–Thermal-Hydraulics–Coupled Transient Analysis for Reactor Power Change in an Inclined Offshore Floating Boiling Water Reactor 

Nuclear Technology 2024年  

Critical Experiment Plans on the New STACY to Clarify the Criticality Characteristics of the Molten Core-Concrete Interaction Products 

Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024 227-236 2024年  

Application of Monte Carlo Solver Solomon to Critical Mass Calculation of Fuel Randomization System 

Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024 68-77 2024年  

Measurement of spent nuclear fuel burn-up using a new H(n, γ) method 

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 1050 2023年5月  

Absolute quantification of ¹³⁷Cs activity in spent nuclear fuel with calculated detector response function 

Journal of Nuclear Science and Technology 60(6) 615-623 2023年  

Development of Experimental Core Configurations to Clarify k<inf>eff</inf>Variations by Nonuniform Core Configurations 

Nuclear Science and Engineering 197(8) 2017-2029 2023年  

PRELIMINARY EVALUATION OF SIMILARITY BETWEEN THE MODIFIED STACY CORE CONFIGURATIONS AND THE PSEUDO-FUEL DEBRIS MODELS 

International Conference on Nuclear Engineering, Proceedings, ICONE 2023-May 2023年  

Evaluation of critical experimental core configurations to simulate nonuniform fuel debris 

Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022 3396-3405 2022年  

確率論的幾何形状モデルの軽水体系への適用について—Applicability of Statistical Geometry Model to Light Water Moderating Systems 

JAEA-research 2018(10) 2019年2月  

Analyses of used BWR fuel assay data with the integrated burnup code system SWAT4.0 

Journal of Nuclear Science and Technology 55(2) 138-150 2018年2月1日  

SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data 

Annals of Nuclear Energy 110 779-788 2017年12月  

FRENDY: A new nuclear data processing system being developed at JAEA 

EPJ Web of Conferences 146 2017年9月13日  

Investigation to reduce mass of a ultra-light solid reactor for electricity supply in environments without human maintenance 

2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017年  

Development of an automatic nuclear data validation system VACANCE 

2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017年