1.20 CORE MANAGEMENT FOR DALAT NUCLEAR RESEARCH REACTOR BY SRAC CODE

摘要

The paper presents all results calculation in neutronic for Dalat Nuclear Research Reactor (DNRR) by SRAC Code. The calculated results from the SRAC code were compared with experimental data and those obtained by MCNP code to verify and validation of this code to the DNRR. The obtained results were found to be in good agreement with experimental data. This is allowable to confirm that the SRAC code is a suitable neutronic code system for DNRR and is available for replacing the former codes. The application of the SRAC code for DRR is included: Calculation of macroscopic group cross-sections for fuel and non-fuel cells (PIJ,ANISN), calculation of heavy nuclides and fission products (PIJ), calculation of kinetic parameters, temperature coefficients of moderator and fuel (CITATION), burn-up calculation and core management ( COREBN). MVP/GMVP Code also was applied for DNRR in cell and cell burn-up calculation, whole core calculation including core burn up are under researching.