ANS answers inquiry on ANSI/ANS-6.4-2006

摘要

The ANS Standards Committee received an inquiry determined to be a request for clarification. The inquiry and response are provided below.rnANSI/ANS-6.4-2006, Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants.rnInquiry: I performed a shielding calculation at the concrete surface of a spent fuel storage facility using the Monte Carlo N-Particle Transport Code, Version 4C, and the QAD-CGGP-A, a point-kernel code forrncalculating fast-neutron and gamma-ray penetration through various shield configurations defined by combinatorial geometry specifications.