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ANS 19.1

2002 Edition, 2002

Complete Document

nuclear data sets for reactor design calculations

Includes all amendments and changes through Reaffirmation Notice , 2011

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Product Details:

  • Revision: 2002 Edition, 2002
  • Published Date: June 17, 2011
  • Status: Active, Most Current
  • Document Language: English
  • Published By: American Nuclear Society (ANS)
  • Page Count: 17
  • ANSI Approved: Yes
  • DoD Adopted: No

Description / Abstract:


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.


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.