DPA calculation for the first generation of VVER-440 dual purpurose cask
Date issued
2023
Journal Title
Journal ISSN
Volume Title
Publisher
Institute of Nuclear Materials Management
Abstract
Radiation damage can be assessed by displacements per atom. DPA calculations can be performed with flux conversion functions for stainless steels by ASTM or IRDFF standards or with damage cross sections for arc-DPA and NRT-DPA definitions. In the paper, DPA calculations of borated steel, aluminum alloy and cast iron as the most affected materials in the first generation of VVER-440 dual purpose spent fuel cask is presented. DPA rate calculated by damage energy cross sections from BROND, CENDL, ENDF/B, JEFF, JENDL and RUSFOND libraries and functions from ASTM and IRDFF standards were compared on simplified spent fuel cask model with MCNP6 calculation code. The aim of the paper is to present which cross sections are conservative for various types of materials and how long-term storage would affect total DPA for the cask materials.
Description
Subject(s)
radiation damage, displacements per atom, spent fuel cask, Monte Carlo