Nuclear Analysis of PIE Data of Irradiated BWR 8×8-2 and 8×8-4 UO₂Fuel Assemblies

Abstract

The measured pellet average inventories of actinides and fission product nuclides on the fifteen samples taken from a three-cycle irradiation BWR 8Â8-2 UO 2 assembly were compared with those of assembly burnup calculations using a collision probability method (SRAC) with the JENDL-3.2 nuclear data library. Am. The major FP nuclides contributing to neutron absorption such as Nd, Cs, Eu, and Sm are almost well reproduced by the present calculations. The measured pellet average burnups and major actinide inventories on the twenty samples taken from four BWR 8Â8-4 UO 2 assemblies were also compared with those of the burnup calculations using SRAC and a continuous energy Monte Carlo burnup analysis code (MVP-BURN). Most of the calculated pellet average burnups of both codes agree with the measurements within the range of AE10%. The general trends of the measured pellet radial distributions of actinide and FP nuclides on six samples of the 8Â8-4 UO 2 assemblies were well reproduced by the burnup calculations of MVP-BURN.

Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled Neutronics/Thermal-Hydraulics Simulations

“…e first benchmark used in analysis is the 2F2D1 BWR assembly from the Fukushima Daini-2 reactor. e design is 8 × 8-4 with 60 fuel rods and one water rod [20]. e top portion of Figure 1 presents the radial layout of the assembly.…”