ASTM International - ASTM E1018-20e1

Standard Guide for Application of ASTM Evaluated Cross Section Data File

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Organization: ASTM International
Publication Date: 1 March 2020
Status: active
Page Count: 9
ICS Code (IT applications in industry): 35.240.50
significance And Use:

4.1 The ENDF/B library in the United States and similar libraries elsewhere, such as JEFF (23), JENDL (21), and BROND (22), provide a compilation of neutron cross section and... View More

scope:

1.1 This guide covers the establishment and use of an ASTM evaluated nuclear data cross section and uncertainty file for analysis of single or multiple sensor measurements in neutron fields related to light water reactor LWR-Pressure Vessel Surveillance (PVS). These fields include in- and ex-vessel surveillance positions in operating power reactors, benchmark fields, and reactor test regions.

1.2 Requirements for establishment of ASTM-recommended cross section files address data format, evaluation requirements, validation in benchmark fields, evaluation of error estimates (covariance file), and documentation. A further requirement for components of the ASTM-recommended cross section file is their internal consistency when combined with sensor measurements and used to determine a neutron spectrum.

1.3 Specifications for use include energy region of applicability, data processing requirements, and application of uncertainties.

1.4 This guide is directly related to and should be used primarily in conjunction with Guides E482 and E944, and Practices E560, E185, and E693.

1.5 The ASTM cross section and uncertainty file represents a generally available data set for use in sensor set analysis. However, the availability of this data set does not preclude the use of other validated data, either proprietary or nonproprietary. When alternate cross section files that deviate from the requirements laid out in this standard are used, the deviations should be noted to the customer of the dosimetry application.

1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.

1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Document History

March 1, 2020
Standard Guide for Application of ASTM Evaluated Cross Section Data File
4.1 The ENDF/B library in the United States and similar libraries elsewhere, such as JEFF (23), JENDL (21), and BROND (22), provide a compilation of neutron cross section and other nuclear data for...
ASTM E1018-20e1
March 1, 2020
Standard Guide for Application of ASTM Evaluated Cross Section Data File
4.1 The ENDF/B library in the United States and similar libraries elsewhere, such as JEFF (23), JENDL (21), and BROND (22), provide a compilation of neutron cross section and other nuclear data for...
June 1, 2013
Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)
4.1 The ENDF/B library in the United States and similar libraries elsewhere, such as JEF (9), JENDL (7), and BROND (8), provide a compilation of neutron cross section and other nuclear data for use...
June 1, 2013
Standard Guide for Application of ASTM Evaluated Cross Section Data File
4.1 The ENDF/B library in the United States and similar libraries elsewhere, such as JEF (22), JENDL (19), and BROND (20), provide a compilation of neutron cross section and other nuclear data for...
June 1, 2009
Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
The ENDF/B library in the United States and similar libraries elsewhere, such as JEF (9), JENDL (7), and BROND (8), provide a compilation of neutron cross section and other nuclear data for use by...
June 10, 2001
Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
1.1 This guide covers the establishment and use of an ASTM evaluated nuclear data cross section and uncertainty file for analysis of single or multiple sensor measurements in neutron fields r elated...
June 10, 2001
Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
1.1 This guide covers the establishment and use of an ASTM evaluated nuclear data cross section and uncertainty file for analysis of single or multiple sensor measurements in neutron fields r elated...
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