2022 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[2D01-05] Analysis Code Development

Thu. Mar 17, 2022 10:30 AM - 12:00 PM Room D

Chair: Masahiro Tatsumi (NEL)

11:00 AM - 11:15 AM

[2D03] A development of Multi-Physics Burnup Analysis System

(2)Implementation of Burnup Analysis Function with Fuel Assembly Geometry

*Motomu Suzuki1 (1. CRIEPI)

Keywords:Burnup calculation, Assembly Geometry Burnup calculation, OECD/NEA Phase III-C Benchmark, COMPASS, MVP-BURN

An integrated burnup calculation system in order to perform large-scale burnup calculations for multi-assembly and full core geometry and neutronics thermal hydraulics coupling calculation have been developing. In this paper, the implementation and the verification of burnup calculation function with assembly geometry problem are reported.