Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor

Mochizuki, Hiroyasu

doi:10.1080/00223131.2022.2131647

Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor

Journal Article · 19 October 2022 · Journal of Nuclear Science and Technology (Tokyo)

DOI:https://doi.org/10.1080/00223131.2022.2131647· OSTI ID:2424230

Mochizuki, Hiroyasu ^[1]

Laboratory for Zero-Carbon Energy, Institute of Innovative Research, Tokyo Institute of Technology, Meguro-ku, Japan

Not provided.

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE

DOE Contract Number:: AC07-05ID14517

OSTI ID:: 2424230

Journal Information:: Journal of Nuclear Science and Technology (Tokyo), Journal Name: Journal of Nuclear Science and Technology (Tokyo) Journal Issue: 6 Vol. 60; ISSN 0022-3131

Publisher:: Taylor & Francis

Country of Publication:: United States

Language:: English

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