令和３年度 研究成果

Y. Fukaya, S. Okita, S. Nakagawa, M. Goto, H. Ohashi, X. L. Yan

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

Annals of Nuclear Energy, 168, p.108911_1 - 108911_7, 2022/04

Y. Fukaya, S. Ueta, T. Yamamoto, Y. Chikazawa, X. L. Yan

Toxicity Reduction with Total Volume Control in Nuclear Waste

Nuclear Technology, 208(2), p.335 - 346, 2022/02

T. Nishihara

Restart of HTTR

原子力機構・原研OB会会報,80号, P. 2, 2022/01

M. Ono, A. Shimizu, H. Ohashi, S. Hamamoto, H. Inoi, K. Tokuhara^*, Y. Nomoto^*, Y. Shimazaki, K. Iigaki, M. Shinozaki

Seismic classification of high temperature engineering test reactor

Nuclear Engineering and Design, 386, p.111585_1 - 111585_9, 2022/01

Y. Fukaya, M. Goto

Reduction of the source term of an assumed criticality accident in a fuel fabrication facility with solution system

Annals of Nuclear Energy, 164, p.108617_1 - 108617_6, 2021/12

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

Comparisons between passive RCCSS on degree of passive safety features against accidental conditions and methodology to determine structural thickness of scaled-down heat removal test facilities

Annals of Nuclear Energy, 162, p.108512_1 - 108512_10, 2021/11

N. Fujimoto^*, K. Tada, H. Q. Ho, S. Hamamoto, S. Nagasumi, E. Ishitsuka

Nuclear data processing code FRENDY; A Verification with HTTR criticality benchmark experiments

Annals of Nuclear Energy, 158, p.108270_1 - 108270_8, 2021/08

O. Myagmarjav, A. Shibata^*, N. Tanaka, H. Noguchi, S. Kubo, M. Nomura^*, H. Takegami

Fabrication, permeation, and corrosion stability measurements of silica membranes for HI decomposition in the thermochemical iodine-sulfur process

International Journal of Hydrogen Energy, 46(56), p.28435 - 28449, 2021/08

S. Ueta, K. Sasaki, Y. Arita^*

Concepts and basic designs of various nuclear fuels, 5; Fuels for high temperature gas-cooled reactor and molten salt reactor

AESJ ATOMOΣ, 63(8), p.615 - 620, 2021/08

N. Tanaka, S. Sawada^*, T. Yamaki^*, T. Kodaira^*, T. Kimura^*, M. Nomura^*

Improvement of HI concentration performance for hydrogen production iodine-sulfur process using crosslinked cation-exchange membrane

Chemical Engineering Science, 237, p.116575_1 - 116575_11, 2021/06

H. Q. Ho, N. Fujimoto^*, S. Hamamoto, S. Nagasumi, M. Goto, E. Ishitsuka

Preparation for restarting the high temperature engineering test reactor: Development of utility tool for auto seeking critical control rod position

Nuclear Engineering and Design, 377, p.111161_1 - 111161_9, 2021/06

S. Atkinson^*, T. Aoki, D. Litskevich^*, B. Merk^*, X. L. Yan

Part 3, Evaluating a small modular high temperature reactor design during control rod withdrawal and a depressurised loss of coolant accidents

Progress in Nuclear Energy, 134, p.103689_1 - 103689_10, 2021/04

S. Hamamoto, E. Ishitsuka, S. Nakagawa, M. Goto, H. Matsuura^*, K. Katayama^*, T. Otsuka^*, K. Tobita^*

Study on chemical form of tritium in coolant helium of high temperature gas cooled reactor with tritium production device

2021 International Congress on Advances in Nuclear Power Plants (ICAPP 2021), 2021/10

S. Hamamoto, H. Ohashi, K. Iigaki, Y. Shimazaki, M. Ono, A. Shimizu, E. Ishitsuka

Proposal of evaluation method of graphite incombustibility

2021 International Congress on Advances in Nuclear Power Plants (ICAPP 2021), 2021/10

Hai Quan Ho, N. Fujimoto^*, S. Hamamoto, S. Nagasumi, M. Goto, E. Ishitsuka

Calculation of control rods position for restarting the high temperature engineering test reactor

10th International Topical Meeting on High Temperature Reactor Technology (HTR 2021), 2021/06

Department of HTTR

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY2019)

JAEA-Review 2021-017, 81 Pages, 2021/11

E. Ishitsuka, W. Mitsui^*, Y. Yamamoto^*, K. Nakagawa^*, H. Q. Ho, T. Ishii, S. Hamamoto, S. Nagasumi, K. Takamatsu, I. Kenzhina^*, Y. Chikhray^*, H. Matsuura^*, N. Fujimoto^*

Report of summer holiday practical training 2020; Feasibility study on nuclear battery using HTTR core; Feasibility study for nuclear design, 3

JAEA-Technology 2021-016, 16 Pages, 2021/09

D. Tochio, S. Nagasumi, H. Inoi, S. Hamamoto, M. Ono, S.Kobayashi, T. Uesaka, S. Watanabe, K. Saito

Impact assessment for internal flooding in HTTR (High temperature engineering test reactor)

JAEA-Technology 2021-014, 80 Pages, 2021/09

N. Fujimoto^*, K. Fukuda^*, Y. Honda^*, D. Tochio, H. Q. Ho, S. Nagasumi, T. Ishii, S. Hamamoto, Y. Nakano^*, E. Ishitsuka

Mesh effect around burnable poison rod of cell model for HTTR fuel block

JAEA-Technology 2021-008, 23 Pages, 2021/06