ASTM E482 – Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
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.
Product Details
Published:
07/01/2022
Number of Pages:
5
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1 file , 100 KB
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