GAMMA-RAY AND NEUTRON DOSE-EQUIVALENT BUILDUP FACTORS FOR INFINITE SLABS

被引：2

作者：

DUNN, WL ^{[1
]}

YACOUT, AM ^{[1
]}

OFOGHLUDHA, F ^{[1
]}

RIEL, G ^{[1
]}

机构：

[1] USN,CTR SURFACE WARFARE,WHITE OAK LAB,SILVER SPRING,MD 20903

来源：

NUCLEAR SCIENCE AND ENGINEERING | 1992年 / 110卷 / 02期

关键词：

D O I：

10.13182/NSE92-A23883

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Gamma-ray and neutron dose-equivalent buildup factors are calculated for six common shielding materials in a point-source, infinite-slab, point-detector geometry using a decomposition of the solution to the transport problem into single- and multiple-scatter components. A rigorous solution for the single-scatter component is constructed and a Monte Carlo model for the multiple-scatter component is employed. Simplified models are fit to the calculated buildup factors as functions of slab thickness and source-detector separation, and model constants are evaluated for each of several source energies. Single-scatter and total slab buildup factors are presented, both in tabular form and in graphs that also show the fitted models, for six materials. The models are demonstrated for a sample problem.

引用

页码：134 / 156

页数：23

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