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 nuclearfuel
cycle criticality safety. This paper discusses criticality safety benchmarkcalculation
at STACY facility, which uses uranyl nitrate solution with MCNP-4C MonteCarlo
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 uranylnitrate solution at STACY 280T slab core.
Penulis: Zuhair, Suwoto, dan
Suharno
Kode Jurnal: jpfisikadd110166
