RADIATION DOSE CALCULATION FOR FUEL HANDLING FACILITY CLOSURE CELL EQUIPMENT

Musat, D.

United States. Department of Energy. Yucca Mountain Project Office.

关键词: Radiation Doses;    Attenuation;    Photons;    Geometry;    Closures;   

DOI  :  10.2172/859178
RP-ID  :  210-00C-HW00-00100-000-00A REV 00A
RP-ID  :  NA
RP-ID  :  859178

美国|英语

来源: UNT Digital Library

【 摘 要 】

This calculation evaluates the energy deposition rates in silicon, gamma and neutron flux spectra at various locations of interest throughout FHF closure cell. The physical configuration features a complex geometry, with particle flux attenuation of many orders of magnitude that cannot be modeled by computer codes that use deterministic methods. Therefore, in this calculation the Monte Carlo method was used to solve the photon and neutron transport. In contrast with the deterministic methods, Monte Carlo does not solve an explicit transport equation, but rather obtain answers by simulating individual particles, recording the aspects of interest of their average behavior, and estimates the statistical precision of the results.