Verification of a two-step code system MCS/RAST-F to fast reactor core analysis

Verification of a two-step code system MCS/RAST-F to fast reactor core analysis

Blog Article

RAST-F is a new full-core analysis code based on the two-step approach that couples a multi-group cross-section generation Monte-Carlo code MCS and a multi-group nodal diffusion solver.To demonstrate the feasibility of using MCS/RAST-F for fast reactor analysis, this paper presents the coupled nodal product code verification results for the MET-1000 and CAR-3600 benchmark cores.Three different multi-group cross-section calculation schemes are employed to improve the agreement between the nodal and reference solutions.The reference solution is obtained by the MCS welding sweater code using continuous-energy nuclear data.

Additionally, the MCS/RAST-F nodal solution is verified with results based on cross-section generated by collision probability code TULIP.A good agreement between MCS/RAST-F and reference solution is observed with less than 120 pcm discrepancy in keff and less than 1.2% root-mean-square error in power distribution.This study confirms the two-step approach MCS/RAST-F as a reliable tool for the three-dimensional simulation of reactor cores with fast spectrum.