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ASTM E482-16 + Redline

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ASTM E482-16 + Redline

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 E944 and Practice E853 define appropriate computational procedures.

Author ASTM
Editor ASTM
Document type Standard
Format File
ICS 75.080 : Petroleum products in general
Number of pages 5
Replace ASTM E482-11e1 + Redline
Set ASTMVOL1202
Year 2016
Document history ASTM E482-11e1 + Redline
Country USA
Keyword ASTM 482;ASTM E482;ASTM E482;10.1520/E0482-16