Analysis of post irradiation examination data of samples from Obrigheim PWR with re-evaluation of burnup values by neodymium-148 method using the latest nuclear data libraries

Sugino, Hiroyuki; Suyama, Kenya; Okuno, Hiroshi  

Accurate calculation the isotopic composition of spent nuclear fuels (SNF) is important to evaluate the criticality safety of fuel cycle facilities. In the burnup calculation, the burnup value is traditionally used to obtain the exposure value of PIE samples. Because calculation codes and data libraries have been revised progressively, re-evaluation of the burnup values using the latest nuclear data library and calculation method is important to confirm quality of burnup analysis. Based on this idea, the burnup value of Obrigheim PIE data was re-examined to understand the level of the influence. This study shows that the maximum difference of Nd calculation from experimental results is reduced from 1.0 % to 0.7 % by re-evaluation of the burnup value using latest nuclear data, and the deviation of neutron multiplication factor is approximately 0.5 %.