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%.

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

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