Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5

Analysis of ENRESA BWR samples: nuclide inventory and decay heat

“…This covers the fact that individual calculations can strongly differ, undermining prediction power. This case is relatively similar to the validation of decay heat calculations, as presented in reference [20]: individual cases can show large deviations from C/E = 1, but their average is close to C/E = 1. Finally, one can observe that the prediction of the Cm isotopes is relatively poor, and in the case of 244 Cm, calculated uncertainties do not help understanding differences between C and E (see details in Sect.…”

“…Table 1 summarized the non-proprietary data for GN592 assembly parameters from reference [12]. The assembly GN592 was irradiated for five consecutive cycles (cycle [16][17][18][19][20] from July 24, 2000, and was discharged on May 28, 2005. One can notice that the fuel temperature is provided at a specific burnup value. It is nevertheless recognized that the fuel temperature can vary up to a few hundred degrees as a function of the segment burnup and power [14].…”

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

“…-17 PIE samples were used to calculate nuclide compositions, uncertainties, and biases, for 4 ARIANE samples (GU1, GU3, BM1, BM3), 8 ENRESA samples (not available in SFCOMPO), the U1 PROTEUS sample (also not available in SFCOMPO), 2 Takahama samples (SF95-4 and SF95-5), and 2 Gundremmingen samples (B23-A1-I2680 and C5-B23-K2680), with the addition of 2 computational cases (S1.PWR and krsko.PWR [14,15]), -271 calorimetric measurements from CLAB (labelled herein as CLAB-2006), GE-Morris, HEDL facilities and the "SKB-Vattenfall" blind test were analyzed for the assembly average decay heat [16][17][18][19], and the decay heat from the 17 (not measured) PIE samples. Detailed studies were independently published for a number of cases, see references [20][21][22][23][24][25][26][27][28][29][30][31][32]50]; summaries are presented in Tables 1 and 2. Regarding sensitivity studies presented in Table 1, considerable efforts have been made to address the effect of the irradiation history, as-built manufacturing data and effect of various calculation model approximation on the SNF characterization.…”

Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo

“…The focus is on source terms which are of primary importance for safe, secure, ecological, and economical handling, transport, intermediate storage, and final disposal of SNF [1]. The main source terms of interest are neutron emission rates, γ-ray emission spectra, decay heat rate, and the inventory of specific nuclides, i.e., activation products (e.g., 14 C and 36 Cl), long-lived fission products (FP), fissile nuclides ( 235 U, 239 Pu) and minor actinides ( 241,243 Am, 242,244 Cm). The inventory of fissile nuclides is needed for nuclear safeguards requirements and reactivity calculations to prevent criticality.…”

“…For decay heat, the calorimetric measurements from CLAB (Swedish Central Intermediate Storage Facility), GE-Morris, and HEDL (Hanford Engineering Development Laboratory) were considered, leading to more than 250 cases. To support the recommendations of this subtask, some studies were already published, see references [3][4][5][6][7][8][9][10][11][12][13][14][15]. A global review of the The aim is to produce NDA systems that can be used to provide experimental data to validate the performance of the codes (including nuclear data) and to verify the declared design and operational history of the assemblies.…”