학술논문
NAC-1 cask dose rate calculations for LWR spent fuel
Document Type
Technical Report
Author
Source
Other Information: PBD: 24 Feb 1999
Subject
Language
English
Abstract
A Nuclear Assurance Corporation nuclear fuel transport cask, NAC-1, is being considered as a transport and storage option for spent nuclear fuel located in the B-Cell of the 324 Building. The loaded casks will be shipped to the 200 East Area Interim Storage Area for dry interim storage. Several calculations were performed to assess the photon and neutron dose rates. This report describes the analytical methods, models, and results of this investigation.