ASTM-E482 2011

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E482-11 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)

Published By	Publication Date	Number of Pages
ASTM	2011	5

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Description

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.

Additional information

Standard Title	E482-11 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
Published Code	ASTM
Publication Date	2011
Pages Count	5

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ASTM-E482 2011

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