2024 Annual Meeting

Presentation information

Oral presentation

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

[3D09-13] Methodology Development

Thu. Mar 28, 2024 2:45 PM - 4:05 PM Room D (21Bildg.3F 21-312)

Chair:SHIN KIKUCHI(JAEA)

3:45 PM - 4:00 PM

[3D13] Development of core deformation reactivity evaluation method

(1) Application to the EBR-II SHRT-45R test

*Norihiro Doda1, Shinya Kato1, Kazuo Yoshimura1, Tomoyuki Uwaba1, Kenji Yokoyama1, Masaaki Tanaka1 (1. JAEA)

Keywords:reactivity feedback, core deformation reactivity, coupled analysis, EBR-II, sodium-cooled fast reactor

An evaluation method for reactivity feedback due to core deformation during reactor power variation in sodium-cooled fast reactors has been developed by JAEA for core design optimization. This core deformation reactivity is a complex phenomenon caused by the interaction between reactor physics, thermal-hydraulics, and structural mechanics. To capture the phenomenon, the evaluation method couples the MARBLE code for reactor physics, the Super-COPD code for system-scale thermal-hydraulics, the ASFRE code for fuel-assembly-scale thermal-hydraulics, and the FINAS code for core structural deformation. This reports the analysis results of the EBR-II shutdown heat removal test (SHRT)-45R using this evaluation method to understand the physical behaviors related to the core deformation reactivity, and future development issues.

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