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ANS 6.4

Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants

Organization:
ANS - American Nuclear Society
Year: 2006

Abstract: This standard contains methods and data needed to calculate the concrete thickness required for radiation shielding in nuclear power plants. Where possible, specific recommendations are made regarding radiation attenuation calculations, shielding design, and standards of documentation. The standard provides guidance to architect-engineers, utilities, and reactor vendors who are responsible for the shielding design of stationary nuclear plants. This standard does not consider sources of radiation other than those associated with nuclear power plants. It also excludes considerations of economic aspects of shielding design.
Concrete is a mixture of materials, the exact proportions of which will differ from application to application. This standard includes a discussion of the nature of concrete, emphasizing those variable aspects of the material that are important to the shield designer. The document discusses methods of analysis and the shielding input data appropriate to each method. Applications of the analytical methods are given, including bulk transport, radiation heating, streaming, and reflection problems.
URI: https://yse.yabesh.ir/std/handle/yse/2537
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contributor authorANS - American Nuclear Society
date accessioned2017-09-04T15:05:06Z
date available2017-09-04T15:05:06Z
date copyright01/01/2006
date issued2006
identifier otherLBBPYBAAAAAAAAAA.pdf
identifier urihttps://yse.yabesh.ir/std/handle/yse/2537
description abstractThis standard contains methods and data needed to calculate the concrete thickness required for radiation shielding in nuclear power plants. Where possible, specific recommendations are made regarding radiation attenuation calculations, shielding design, and standards of documentation. The standard provides guidance to architect-engineers, utilities, and reactor vendors who are responsible for the shielding design of stationary nuclear plants. This standard does not consider sources of radiation other than those associated with nuclear power plants. It also excludes considerations of economic aspects of shielding design.
Concrete is a mixture of materials, the exact proportions of which will differ from application to application. This standard includes a discussion of the nature of concrete, emphasizing those variable aspects of the material that are important to the shield designer. The document discusses methods of analysis and the shielding input data appropriate to each method. Applications of the analytical methods are given, including bulk transport, radiation heating, streaming, and reflection problems.
languageEnglish
titleANS 6.4num
titleNuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plantsen
typestandard
page96
statusActive
treeANS - American Nuclear Society:;2006
contenttypefulltext
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