Modeling Gamma-Ray Dose Rate from a Spent Pressurized Water Reactor Fuel Assembly
Abstract
Gamma-ray dose rate distribution around a pressurized water reactor spent-fuel assembly is studied using the Monte Carlo N-particle transport code (MCNP) version 4a. A detailed rod-by-rod modeling of the assembly is utilized, showing explicitly the fuel, cladding, control rod channels, and the instrumentation tube. A cylindrically distributed source of gamma rays, within every fuel rod, is considered with a seven-group energy spectrum. Dose rates are obtained by tallying the gamma rays at several axial and radial positions outside the assembly. The results indicate that the radial distribution of the dose rate can be represented by a power relationship of the form r-n, where r is the radial distance from the assembly center. Another important conclusion from this study is that the dose rate close to the assembly surface is overestimated if a homogeneous assembly model is used.
Recommended Citation
A. Bozkurt and N. Tsoulfanidis, "Modeling Gamma-Ray Dose Rate from a Spent Pressurized Water Reactor Fuel Assembly," Nuclear Technology, vol. 119, no. 1, pp. 38 - 47, Taylor and Francis Group; Taylor and Francis; American Nuclear Society, Jan 1997.
The definitive version is available at https://doi.org/10.13182/NT77-A35393
Department(s)
Nuclear Engineering and Radiation Science
Keywords and Phrases
Gamma dose; MCNP; Spent fuel
International Standard Serial Number (ISSN)
0029-5450
Document Type
Article - Journal
Document Version
Citation
File Type
text
Language(s)
English
Rights
© 2024 Taylor and Francis Group; Taylor and Francis; American Nuclear Society, All rights reserved.
Publication Date
01 Jan 1997
