ASTM PAPERS-FOREWORD

摘要

This Seminar* on Accelerated Testing of Materials in Spent Nuclear Fuel and High Level Waste Storage Systems focused on the role and understanding of accelerated testing to qualify materials for spent nuclear fuel (SNF) and storage of vitrified HLW and repository systems, noting the conclusions and issues raised in the Jan 26-27, 2005 seminar; it also included a workshop on surveillance and performance evaluation systems. The identification of related important alteration mechanisms to qualify1 materials used for HLW glass and spent nuclear fuel interim dry storage systems and repositories was also addressed. The ability of the cask materials used in interim storage, and the components of the engineered barrier system (waste form, waste package, backfill, etc) used in repository disposal to contain and control radionuclide release, and maintain criticality control and shielding capability was discussed.