2020 Annual Meeting

Presentation information

Oral presentation

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

[2I08-11] Development of Analysis Method & Code 1

Tue. Mar 17, 2020 2:45 PM - 3:50 PM Room I (Lecture Bildg. M 2F M-23)

Chair:Go Chiba(Hokkaido Univ.)

2:45 PM - 3:00 PM

[2I08] Development of a Monte Carlo Solver Solomon for Criticality Safety Analysis

(3)Implementation of Thermal Neutron Scattering Models

*Yasunobu Nagaya1 (1. JAEA)

Keywords:Criticality safety, Monte Carlo solver, Solomon, Thermal neutron scattering models

In order to build a criticality characteristics database for fuel debris, a Monte Carlo Solver Solomon has been under development. Thermal neutron scattering models have been implemented into Solomon to extend the applicability area to thermal reactor systems. The implementation has been verified with the inter-code comparison of effective multiplication factors for simple geometries.