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ASTM E482

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

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Organization: ASTM
Publication Date: 1 June 2011
Status: inactive
Page Count: 5
scope:

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.

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.

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
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 1, 2011
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
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...
ASTM E482
June 1, 2011
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
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 1, 2007
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
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)
Scope 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...
October 27, 1989
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E 706 (IID)
1. 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...
May 28, 1982
STANDARD GUIDE FOR APPLICATION OF NEUTRON TRANSPORT METHODS FOR REACTOR VESSEL SURVEILLANCE, E 706(IID) (E1-1985)
A description is not available for this item.

References

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