Validation of decay heat calculation results of ORIGEN2.2 and CASMO5 for light water reactor fuel

Abstract

Comparing with the fission product nuclide (FP) decay heat summation calculation result in MeV/sec/fission based on the JENDL FP decay and yield data files 2011 for the burst fission, FP decay heat calculated by ORIGEN2.2 coupled with JENDL-4.0 base library ORLIBJ40 was verified at the cooling time from 1 sec to 10 8 sec for 235 U (thermal), 238 U (fast), 239 Pu (thermal) and 241 Pu (thermal). For these fission nuclides, FP decay heat calculated by CASMO5 at the same cooling time after a short irradiation (10 4 sec) was also compared with that of ORIGEN2.2. In the analysis of decay heat measurements at the cooling time from 2.3 years to 27 years consisting of four data sets on the fuel assemblies discharged from the US PWRs and BWRs, and the Swedish PWRs and BWRs, the average values of the ratios of the calculated to measured results (C/E's) were from 0.972 to 1.031 for ORIGEN2.2, and from 0.977 to 1.016 for CASMO5. The standard deviations of C/E's for the four data sets were from 0.02 to 0.03 for the both codes except for those of the US BWR fuel assemblies which were from 0.11 to 0.12. The obtained C/E's were similar to those in the precedent study.

On the estimation of nuclide inventory and decay heat: a review from the EURAD European project

“…[30,44] for details) as well as some analysis from the open literature (see Refs. [13,61]) is presented in Figure 7. In this figure, one C/E value represents the average of all cases presented in the specific reference.…”

Validation of the burnup code MOTIVE with respect to fuel assembly decay heat data

“…The corresponding decay heat is dominated by 60 Co which has a half-life of 5.3 years. According to (Yamamoto and Iwahashi, 2016) the influence of activation should be negligible for the Cooper assemblies, due to zircaloy being used for the spacer grids instead of inconel. For the cooling time range of the CLAB assemblies the contribution should be small.…”

Analysis for the ARIANE GU3 sample: nuclide inventory and decay heat

“…Calculated uncertainties for each isotope are presented in Tables B. 4 and B.5. The first remark is that generally, the uncertainties due to nuclear data are the dominant ones.…”

“…The present study contributes to such validation efforts for the CASMO5 transport code [1][2][3][4]. The calculated nuclide inventory for the relocated Post Irradiation Examination sample GU3 from the ARIANE program [5] will be presented and compared to measurements, and calculated uncertainties as well as biases will be proposed.…”