Analisis Perhitungan Benchmark Keselamatan Kritikalitas Larutan Uranil Nitrat di Teras Slab 280T STACY

Abstract

Criticality benchmark experiment at STACY critical facility is important for validation of computation technique and nuclear data library used in design of nuclear fuel cycle criticality safety. This paper discusses criticality safety benchmark calculation at STACY facility, which uses uranyl nitrate solution with MCNP-4C Monte Carlo transport code. The continuous energy nuclear data library was utilized in benchmark calculation to complete criticality safety analysis. The MCNP-4C criticality (keff) prediction indicated overestimated results for all configurations except for configuration 131. The biases of calculation with criticality experiment (keff = 1) were under 0.26%. Configuration 140 calculation showed the most precisely agreement with C/E value of 1.0001. From these results, it can be concluded that the capability and reliability of MCNP-4C is constantly high in prediction of criticality accuracy for uranyl nitrate solution at STACY 280T slab core.

Keywords

• criticality, uranyl nitrate solution, stacy, slab core, mcnp-4c