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ANS 19.1

nuclear data sets for reactor design calculations

Organization:
ANS - American Nuclear Society
Year: 2011

Abstract: General
This standard identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include ~a! criteria for acceptance of evaluated nuclear data sets; ~b! criteria for processing evaluated data and preparation of processed continuous data and averaged data sets; and ~c! identification of specific evaluated, processed continuous, and averaged data sets that meet these criteria for specific reactor types.
Applications
Nuclear data sets shall consist of basic microscopic nuclear physics data that include but are not limited to the important neutroninduced reactions. The data set, in the processed form, will be primarily utilized as input to fission reactor core design calculations but may have applications to other fields, such as shielding, dosimetry, or fusion studies. The specific types of data sets considered to fall within the scope of this standard are shown in Figure 1 and defined more precisely in Section 2, "Definitions." As indicated in Figure 1, the scope of this standard does not pertain to experimental techniques for the measurement of nuclear data or to the development of nuclear model theory. The scope does not apply to a few-group collapsed data set, which is representative of a particular application except for a requirement for the documentation of collapsed data sets when such data sets are prepared as part of the testing of the nuclear data sets covered by this standard. The distinguished features of data sets considered to fall within the scope of this standard are that they can be represented as being applicable to a wide range of reactor compositions, geometries, and spectra.
URI: https://yse.yabesh.ir/std/handle/yse/141824
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contributor authorANS - American Nuclear Society
date accessioned2017-09-04T17:18:29Z
date available2017-09-04T17:18:29Z
date copyright06/23/2002 (R 2011)
date issued2011
identifier otherCCBPTEAAAAAAAAAA.pdf
identifier urihttps://yse.yabesh.ir/std/handle/yse/141824
description abstractGeneral
This standard identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include ~a! criteria for acceptance of evaluated nuclear data sets; ~b! criteria for processing evaluated data and preparation of processed continuous data and averaged data sets; and ~c! identification of specific evaluated, processed continuous, and averaged data sets that meet these criteria for specific reactor types.
Applications
Nuclear data sets shall consist of basic microscopic nuclear physics data that include but are not limited to the important neutroninduced reactions. The data set, in the processed form, will be primarily utilized as input to fission reactor core design calculations but may have applications to other fields, such as shielding, dosimetry, or fusion studies. The specific types of data sets considered to fall within the scope of this standard are shown in Figure 1 and defined more precisely in Section 2, "Definitions." As indicated in Figure 1, the scope of this standard does not pertain to experimental techniques for the measurement of nuclear data or to the development of nuclear model theory. The scope does not apply to a few-group collapsed data set, which is representative of a particular application except for a requirement for the documentation of collapsed data sets when such data sets are prepared as part of the testing of the nuclear data sets covered by this standard. The distinguished features of data sets considered to fall within the scope of this standard are that they can be represented as being applicable to a wide range of reactor compositions, geometries, and spectra.
languageEnglish
titleANS 19.1num
titlenuclear data sets for reactor design calculationsen
typestandard
page17
statusActive
treeANS - American Nuclear Society:;2011
contenttypefulltext
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