2024 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[3D06-08] Behaviors of FP and Hydrogen

Thu. Mar 28, 2024 11:05 AM - 11:55 AM Room D (21Bildg.3F 21-312)

Chair:Junichi Kaneko(NRA)

11:05 AM - 11:20 AM

[3D06] Study of FP transport behavior through TeRRa-CsOH experimental analysis using FP behavior analysis code FIPRA

*Yoshihiro Morita1, Masanori Naitoh1 (1. AdvanceSoft)

Keywords:Severe accident, fission product, FIPRA

Fission products (FPs) generated during severe accidents in light water reactors (LWRs) migrate over a wide area and are considered to have a significant impact on contamination inside and outside the reactor. Therefore, accurate prediction of FP behavior during accidents is considered to be important for reactor safety assessment.
In this study, the TeRRa-CsOH experimental analysis was performed using the FP behavior analysis code FIPRA to evaluate the wall adsorption behavior of FP.

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