Validation of the SRAC code on the first core of RSG-GAS reactor

The validation of the SRAC code on the experimental results of the first core of RSG GAS reactor has been carried out in this work. The validation covers some neutronic core parameters, such as the effective multiplication factor, excess reactivity, control rod worth and the average thermal neutron flux. The validation works are carried out using PIJ, ANISN and CITATION in SRAC version of 2002. In the core calculations, eight energy groups of neutron cross-section of core materials are using. The calculation results showed that the relative difference from experimental results for control rod and excess reactivity are in the range of 0.01%-5.6% and 5.7%-7.1%, respectively. For the average thermal neutron flux, the calculated results are 11% lower compared to the experimental results at D-6 core grid position. It is concluded that the SRAC code producing the calculated results quite good agreement with the experimental results. (author)