Features of Burnup Calculations in the SERPENT 2 Software Package Using the Example of a BWR Fuel Assembly
Abstract
In this paper, we used the data from “OECD/NEA Burnup Credit Criticality Benchmark Phase IIIB: Nuclide Composition and Neutron Multiplication Factor of BWR Spent Fuel Assembly” ([1]) for the verification of the SERPENT 2 code. The results obtained which were compared with the results of other authors, which were also given in “OECD/NEA Burnup Credit Criticality Benchmark Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport” ([2]). Investigations of the influence of the detailed model of pins and pins with gadolinium, as well as various methods of burn-up calculations were also carried out.
References
[1] Hiroshi OKUNO, Yoshitaka NAITO. “OECD/NEA Burnup Credit Criticality Benchmark Phase IIIB: Nuclide Composition and Neutron Multiplication Factor of BWR Spent Fuel Assembly”. Japan Atomic Energy Research Institute/ November 1996.
[2] Hiroshi OKUNO, Yoshitaka NAITO and Kenya SUYAMA. JAERI-Research2002-001, “OECD/NEA Burnup Credit Criticality Benchmark Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport”, NEA/NSC/DOC(2002)2. Japan Atomic Energy Research Institute/ February 2002.
[3] Jaakko Leppänen. Serpent – a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code - User’s Manual / June 18, 2015.