ASTM International - ASTM E482-11e1

Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)

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Organization: ASTM International
Publication Date: 1 June 2011
Status: historical
Page Count: 5
ICS Code (Nuclear power plants. Safety): 27.120.20
significance And Use:

3.1 General:

3.1.1 The methodology recommended in this guide specifies criteria for validating computational methods and outlines procedures applicable to pressure vessel related... View More

scope:

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 E944 and Practice E853 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.

Document History

July 1, 2016
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
3.1 General:  3.1.1 The methodology recommended in this guide specifies criteria for validating computational methods and outlines procedures applicable to pressure vessel related neutronics...
June 1, 2011
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
The neutronics methodology is validated, if (in addition to qualitative model evaluation) all of the following criteria are satisfied: (1) The bias, q ¯ , is less than ε1 General: The methodology...
ASTM E482-11e1
June 1, 2011
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
3.1 General: 3.1.1 The methodology recommended in this guide specifies criteria for validating computational methods and outlines procedures applicable to pressure vessel related neutronics...
June 1, 2007
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
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...
June 10, 2001
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
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...
June 10, 2001
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
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...
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