Formulas Giving Buildup Factor for Double-layered Shields
Abstract
Formulas that give absorbed dose buildup factors for two-layered shields have been developed based on gamma-ray absorption buildup factors computed with the Monte Carlo Neutral Particle Transport Code System (MCNP). The shielding materials considered were water, lead, steel, concrete, and some of their combinations for two-layered shields with thicknesses between 1 to 10 mfp. Gamma energy considered ranged from 0.5 to 6 MeV. The formulas reproduce MCNP results with a difference of < 10%, in most cases < 3%.
Recommended Citation
M. Guvendik and N. Tsoulfanidis, "Formulas Giving Buildup Factor for Double-layered Shields," Nuclear Technology, vol. 131, no. 3, pp. 332 - 336, Taylor and Francis Group; Taylor and Francis; American Nuclear Society, Jan 2000.
The definitive version is available at https://doi.org/10.13182/NT00-A3120
Department(s)
Nuclear Engineering and Radiation Science
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 2000