2024 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-3 Research Reactor, Application of Neutron

[1L01-03] JRR-3 Advancement

Tue. Mar 26, 2024 10:00 AM - 10:50 AM Room L (21Bildg.4F 21-423)

Chair:Masato Yamamoto(MHI)

10:30 AM - 10:45 AM

[1L03] Basic design of high-performance moderator vessel for JRR-3 cold neutron source

(3)Study on hydrogen flow analysis method

*Sho Tokunaga1, Takemi Nakamura1, Masanobu Kikuchi1, Hironori Noguchi2, Yasushi Oda2 (1. JAEA, 2. MHI)

Keywords:Cold neutron source, CNS, Liquid Hydrogen, Flow analysis

In order to examine a hydrogen flow analysis method for the high-performance moderator vessel including the entire CNS system, a pipe network analysis of the entire system including the moderator vessel using RELAP5/MOD3.2 and a CFD analysis of the moderator vessel using ANSYS-FLUENT which added physical models that were not considered in a conceptual design were evaluated in combination. The validity of these calculations was compared using Sudo’s equation, which is in good agreement with the results of an out-of-reactor operating test in a current canteen bottle moderator vessel.

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