2024 Annual Meeting

Presentation information

Oral presentation

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

[2L10-14] Analysis Code Development

Wed. Mar 27, 2024 2:45 PM - 4:05 PM Room L (21Bildg.4F 21-423)

Chair:Tatsuya Fujita(JAEA)

3:15 PM - 3:30 PM

[2L12] A development of Multi-Physics Burnup Analysis System

(6) Implementation of Interpolation Function of Cross Section for Material Temperature using Pseudo Material Method (Part 2)

*Motomu Suzuki1 (1. CRIEPI)

Keywords:Burnup Calculation, Neutronics-Thermal/hydraulics Coupling Calculation, Multi-Physics Calculation, COMPASS, Pseudo Material Method, MVP3

An integrated burnup calculation system in order to perform large-scale burnup calculations for multi-assembly and full core geometry have been developing. In this paper, the implementation and improvement of interpolation function for material temperature using pseudo material method and the calculation results of neutronics-thermal/hydraulics coupling burnup calculation for pin-cell problem are presented.

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