Results for FY '20

N. Hirota, K. Takeda, Y. Tachibana, Y. Masaki

Corrosion resistance and oxide film structure of stainless steels and Ni-based alloys under sulfuric decomposition gas at high temperature

zairyo-to-kankyo, 70(3), p.68-76, 2021/03

K. Takamatsu, T. Matsumoto, W. Liu, K. Morita

Comparison between passive reactor cavity cooling systems based on atmospheric radiation and atmospheric natural circulation

Annals of Nuclear Energy, 151, p.107867_1 - 107867_11, 2021/02

Y. Fukaya, S. Ueta, M. Goto, H. Ohashi

Feasibility study on burnable poison credit concept to HTGR fuel fabrication from core specification perspective

Annals of Nuclear Energy, 151( ), p.107937_1 - 107937_9, 2021/02

T. Aoki, S. S. Chirayath, H. Sagara

Proliferation resistance evaluation of an HTGR transuranic fuel cycle using PRAETOR code

Annals of Nuclear Energy, 141, p.107325_1 - 107325_7, 2020/06

H. Sato, H. Ohashi

Uncertainty analysis of toxic gas leakage accident in cogeneration high temperature gas-cooled reactor

Mechanical Engineering Journal (Internet), 7(3), p.19-00332_1 - 19-00332_11, 2020/06

S. Takada, I. W. Ngarayana, Y. Nakatsuru, A. Terada, K. Murakami, K. Sawa

Establishment of reasonable 2-D model to investigate heat transfer and flow characteristics by using scale model of vessel cooling system for HTTR

Mechanical Engineering Journal (Internet), 7(3), p.19-00536_1 - 19-00536_12, 2020/06

S. Ueta, N. Mizuta, K. Sasaki, N. Sakaba, H. Ohashi, X. L. Yan

Research and development on high burnup HTGR fuels in JAEA

Mechanical Engineering Journal (Internet), 7(3), p.19-00571_1 - 19-00571_12, 2020/06

I. Ioka, J. Iwatsuki, Y. Kuriki, D. Kawai, H. Yokota, S. Kubo, Y. Inagaki, N. Sakaba

Study of container using hybrid technique for sulfuric acid decomposition of thermochemical water-splitting iodine-sulfur process

Mechanical Engineering Journal (Internet), 7(3), p.19-00377_1 - 19-00377_11, 2020/06

M. Ono, Y. Fujiwara, T. Matsumoto, K. Iigaki

Evaluation of impact with high temperature engineering test reactor using realistic model of stack and reactor building

Transactions of the Atomic Energy Society of Japan, 19(2), p.110 - 120, 2020/06

Y. Fukaya, N. Mizuta, M. Goto, H. Ohashi, X. L. Yan

Conceptual design study of a high performance commercial HTGR for early introduction

Nuclear Engineering and Design, 361, p.110577_1 - 110577_6, 2020/05

Y. Kamiji, H. Noguchi, H. Takegami, N. Tanaka, J. Iwatsuki, S. Kasahara, S. Kubo

Reliability improvements of corrosion-resistant equipment for thermochemical water splitting hydrogen production iodine-sulfur process

Nuclear Engineering and Design, 361, p.110573_1 - 110573_6, 2020/05

Y. Fukaya, M. Goto, H. Ohashi

Self-shielding effect of double heterogeneity for plutonium burner HTGR design

Annals of Nuclear Energy, 138, p.107182_1 - 107182_9, 2020/04

H. Q. Ho, Y. Honda, S. Hamamoto, T. Ishii, S. Takada, N. Fujimoto, E. Ishitsuka

Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor

Journal of Nuclear Engineering and Radiation Science, 6(2), p.021902_1 - 021902_6, 2020/04

H. Sato, T. Aoki, H. Ohashi, X. L. Yan

Research and development for safety and licensing of HTGR cogeneration system

Nuclear Engineering and Design, 360, p.110493_1 - 110493_8, 2020/04

H. Takegami, H. Noguchi, N. Tanaka, J. Iwatsuki, Y. Kamiji, S. Kasahara, Y. Imai, A. Terada, S. Kubo

Development of strength evaluation method of ceramic reactor for iodine-sulfur process and hydrogen production test in Japan Atomic Energy Agency

Nuclear Engineering and Design, 360, p.110498_1 - 110498_6, 2020/04

H. Sato, T. Aoki, H. Ohashi

Guidance for Developing Fuel Design Limit of High Temperature Gas-Cooled Reactor

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 10 Pages, 2020/08

T. Aoki, H. Sato, H. Ohashi

Methodology Development for Transient Flow Distribution Analysis in High Temperature Gas-Cooled Reactor

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 6 Pages, 2020/08

T. Aoki, K. Isaka, H. Sato, H. Ohashi

Development of a Flow Network Calculation Code (FNCC) for High Temperature Gas-Cooled Reactors (HTGRs)

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 7 Pages, 2020/08

T. Shibata, H. Sato, S. Ueta, H. Takegami, S. Takada, K. Kunitomi

VHTR technology development in Japan; Progress of R&D activities for GIF VHTR system

2018 GIF Symposium Proceedings (Internet), p.99 - 106, 2020/05

M. Ono, Y. Hanawa, H. Sonobe, A. Nishimura, N. Sugaya, K. Iigaki

Assessment of the Probability of Aircraft Crashing for HTTR

JAEA-Technology 2020-010

E. Ishitsuka, K. Nakashima, N. Nakagawa, H. Q. HO, T. Ishi, S. Hamamoto, K. Takamatsu, I. Kenzhina, Y. Chikhray, H. Matsuura, N. Fujimoto

Report of Summer Holiday Practical Training 2019; Feasibility Study on Nuclear Battery using HTTR Core -Feasibility Study for Nuclear Design (2)-

JAEA-Technology 2020-008

Sector of Fast Reactor and Advanced Reactor Research and Development

Assessment Report on Research and Development Activities in FY2019 Activity “Research and Development on High Temperature Gas-cooled Reactor and Related Heat Application Technology” (Interim Report)

JAEA-Evaluation 2020-001

S. Nagasumi, K. Matsunaka, N. Fujimoto, T. Ishii, E. Ishitsuka

Study on Control Rod Model in HTTR Core Analysis

JAEA-Technology 2020-003