Lattice physics analysis of measured isotopic compositions of irradiated BWR 9 × 9 UO₂fuel

Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainties

“…Experiments on this fuel were performed by the Japan Atomic Energy Agency (JAEA) in two measurement campaigns. The measurement data, for which calculation-experiment comparisons are discussed herein, were obtained in the second measurement campaign and included isotopes of the major actinides U and Pu and of fission products Cs, Eu, Gd, Mo, Nd, Rh, Ru, Sm, and Tc [7,8]. The first campaign included only measurements for U, Pu, and Nd.…”

Feedback on neutron capture cross sections of 238Pu and 241Am from analyses of measured isotopic compositions of irradiated LWR fuels and MOX core physics experiments

“…Even though C/E-1's obtained by using JENDL-4.0 are not available for the samples in "BWR 9 × 9 UO2 Ac," those for JENDL-3.3 are shown to confirm the trend of the underestimates observed in the burnup analysis with JENDL-3.3. Those shown as "PWR 15 × 15 UO2" and "PWR 15 × 15 MOX" are the analysis results on the mea- [7] and [15], respectively; that of and [13]; that of and [16]; that of + [7]. sured results in the MALIBU program [13,16].…”

“…The burnup calculations of MVP-BURN for both libraries were performed by using a general-purpose chain model (u4cm6fp104bp12T for JENDL-3.3 and u4cm6fp110bp14T for JENDL-4.0). The fuel samples are BWR UO 2 fuels [7,15], and PWR UO 2 and MOX fuels [13]. The C/E-1's shown as "BWR 9 × 9 UO2 FP" are on the measured isotopic compositions which were measured by the Japan Atomic Energy Agency (JAEA) under the experimental program which was aimed at the isotopic composition measurements of U, Pu and major fission product nuclides for fuel samples from three-and five-cycle-irradiation BWR 9 × 9 fuel assemblies discharged from Fukushima Daini Unit 1 [15].…”

“…In recent evaluations of neutron cross sections, the thermal and epithermal cross sections of these isotopes were 2 T. Yamamoto and T. Sakai Even though the isotopic compositions of those nuclides are not large, these differences in the capture cross sections may cause the considerable changes in the isotopic compositions in UO 2 and MOX fuels irradiated in LWRs and in the neutron multiplication factors (k eff 's) of MOX loaded light water cores. The purpose of this paper is to show the effect of the differences in the capture cross sections of 238 Pu on the isotopic compositions of 238 Pu in irradiated UO 2 and MOX fuels irradiated in BWR and PWR cores and that of the differences in the capture cross sections of 238 Pu and 241 Am on the by using the nuclear data libraries published before JENDL-4.0 [7][8][9][10][11][12][13][14][15][16]. The open symbols in Figure 3 show the examples of C/E-1's (calculation/measurement -1) obtained by using JENDL-3.3 as the nuclear data libraries for the continuous energy Monte Carlo burnup calculation code MVP-BURN [17] in the horizontal axis of the measured sample burnups.…”

Development of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9 × 9 Fuel

“…Furthermore, by the introduction of high-resolution inductively coupled plasma mass spectrometry (HR-ICP-MS), the IDM has been applied to lanthanide nuclides. The developed method was applied to the measurement of isotopic composition of used BWR 9 Â 9 fuel and evaluation of the burn-up calculation code was carried out [5].…”