沖田 将一朗

JENDL-5 Benchmarking for Advanced Test Reactor for Preparing Burnup Analysis Using Isotopic Data from HTGR type fuel irradiation tests 

Proceedings of 31st International Conference on Nuclear Engineering (ICONE31) (to be published) 2024年8月  査読有り筆頭著者責任著者

JENDL-5 Benchmarking for Fission Reactor Applications 

Journal of Nuclear Science and Technology 61(1) 2-22 2024年  査読有り

Development of a Surrogate System of a Plant Dynamics Simulation Model and an Abnormal Situation Identification System for Nuclear Power Plants Using Deep Neural Networks 

Nuclear Technology 2024年  査読有り

Molecular dynamic analysis of reactor graphite for preparing thermal neutron scattering law 

Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC 2023) (to be published) 2023年10月  査読有り筆頭著者責任著者

Research on Improvement of HTGR core power-density: (4) Feasibility Study for a Reactor Core 

Proceedings of 30th International Conference on Nuclear Engineering (ICONE 30) (ICONE30-1119) 2023年5月  査読有り筆頭著者責任著者

Core Performance Study of HTGR-SiC for Higher Burn Up: Thorium Based Fuel Loading Pattern 

Proceedings of International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C2023) 1-10 2023年  査読有り

Research on Improvement of HTGR core power-density: (3) Fabrication Process of Dense SiC Matrix Fuel Compacts by Reaction Sintering and Their Thermal Conductivity 

Proceedings of 30th International Conference on Nuclear Engineering (ICONE 30) (ICONE30-1328) 2023年  査読有り

Research on Improvement of HTGR core power-density: (2) Assessment of SiC oxidation behavior under HTGR air ingress accident 

Proceedings of 30th International Conference on Nuclear Engineering (ICONE 30) (ICONE30-1181) 2023年  査読有り

Development Plan for Coupling Technology Between High Temperature Gas-cooled Reactor HTTR and Hydrogen Production Facility (2) Development Plan for Coupling Equipment Between HTTR and Hydrogen Production Facility 

Proceedings of 30th International Conference on Nuclear Engineering (ICONE 30) (ICONE30-1371) 2023年  査読有り

Development Plan for Coupling Technology Between High Temperature Gas-cooled Reactor HTTR and Hydrogen Production Facility (1) Overview of the HTTR Heat Application Test Plan to Establish High Safety Coupling Technology 

Proceedings of 30th International Conference on Nuclear Engineering (ICONE 30) (ICONE30-1320) 2023年  査読有り

Japanese Evaluated Nuclear Data Library version 5: JENDL-5 

Journal of Nuclear Science and Technology 60(1) 1-60 2023年  査読有り

General-purpose nuclear data library JENDL-5 and to the next 

European Physical Journal Web of Conferences 284(14001) 1-7 2023年  査読有り

Study on Evaluation Method of Kernel Migration of TRISO fuel for High Temperature Gas-cooled Reactor 

Nuclear Engineering and Design 399(112033) 1-9 2022年  査読有り

Reactor Physics Experiment on a Graphite-moderated Core to Construct Integral Experiment Database for HTGR 

Nuclear Science and Engineering 197 2251-2257 2022年  査読有り招待有り筆頭著者責任著者

Preliminary core calculation on reactivity compensation for SiC matrix fuel compact HTTR with Er burnable poison and Pu fissile material 

Proceedings of 29th International Conference on Nuclear Engineering; Nuclear Energy the Future Zero Carbon Power (ICONE 29) ICONE29-91703 1-6 2022年  査読有り

Preliminary Experiment in a Graphite-Moderated Core to Avoid Full Mock-up Experiment for the Future First Commercial HTGR 

Proceedings of International Conference on Physics of Reactors; Making Virtual a Reality: Advancements in Reactor Physics to Leap Forward Reactor Operation and Deployment (PHYSOR 2022) 2338-2346 2022年  査読有り筆頭著者責任著者

Computed tomography neutron detector system to observe power distribution in a core with long neutron flight path 

Annals of Nuclear Energy 168 2021年  査読有り

A pseudo-material method for graphite with arbitrary porosities in Monte Carlo criticality calculations 

Journal of Nuclear Science and Technology 58(9) 992-998 2021年  査読有り筆頭著者責任著者

Derivation of ideal power distribution to minimize the maximum kernel migration rate for nuclear design of pin-in-block type HTGR 

Journal of Nuclear Science and Technology 58(1) 9-16 2021年  査読有り筆頭著者責任著者

Neutronic Design of Neutron Moderator on a Reentrant-hole Configuration for Kyoto University Accelerator based Neutron Source (KUANS). 

Transactions of the Atomic Energy Society of Japan 19(3) 178-184 2020年  査読有り筆頭著者責任著者