Radiological Impact of Clad and Containment Failures in at-Reactor Spent Fuel Storage Facilities. Final Report

摘要

The acceptable normal operation release of radioisotopes from an at-reactor dry storage system is derived for ALARA guidelines of 10CFR50 Appendix I. Sample calculations examine the sensitivity of the release to a range of cladding and storage systems failure rates covering a spectrum of joint failure modes. The results strongly indicate that dry storage systems can be built and operated with considerable margin of safety relative to normally acceptable release limits. The methods used may be extended to a variety of storage systems and to specific sites. (ERA citation 08:005044)