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ASTM E482-01

Historical Revision

Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance

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1.1 Need for Neutronics Calculations—An accurate calculation of the neutron fluence and fluence rate at several locations is essential for the analysis of integral dosimetry measurements and for predicting irradiation damage exposure parameter values in the pressure vessel. Exposure parameter values may be obtained directly from calculations or indirectly from calculations that are adjusted with dosimetry measurements; Guide E 944 and Practice E 853 define appropriate computational procedures.

1.2 Methodology—Neutronics calculations for application to reactor vessel surveillance encompass three essential areas: (1) validation of methods by comparison of calculations with dosimetry measurements in a benchmark experiment, (2) determination of the neutron source distribution in the reactor core, and (3) calculation of neutron fluence rate at the surveillance position and in the pressure vessel.

1.3 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 and health practices and determine the applicability of regulatory requirements prior to use.


SDO ASTM: ASTM International
Document Number E482
Publication Date June 10, 2001
Language en - English
Page Count 5
Revision Level 01
Supercedes
Committee E10.05
Publish Date Document Id Type View
July 1, 2022 E0482-22 Revision
July 1, 2016 E0482-16 Revision
June 1, 2011 E0482-11E01 Revision
June 1, 2011 E0482-11 Revision
June 1, 2007 E0482-07 Revision
June 10, 2001 E0482-01 Revision
June 10, 2001 E0482-89R96 Reaffirmation