Published September 2000
| Version v1
Journal article
Formulas Giving Buildup Factor for Double-Layered Shields
Description
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%
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 131
- Journal Issue
- 3
- Journal Page Range
- p. 332-336
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37121200
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- ABSORPTION; BUILDUP; CONCRETES; GAMMA RADIATION; LEAD; MEV RANGE 01-10; MONTE CARLO METHOD; NEUTRAL-PARTICLE TRANSPORT; RADIATION DOSES; SHIELDING MATERIALS; SHIELDS; STEELS; THICKNESS; WATER
- Descriptors DEC
- ALLOYS; BUILDING MATERIALS; CALCULATION METHODS; CARBON ADDITIONS; DIMENSIONS; DOSES; ELECTROMAGNETIC RADIATION; ELEMENTS; ENERGY RANGE; HYDROGEN COMPOUNDS; IONIZING RADIATIONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; METALS; MEV RANGE; OXYGEN COMPOUNDS; RADIATION TRANSPORT; RADIATIONS; SORPTION; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/