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Combining Measurements and 3D Neutron Transport Calculations — A Powerful Tool in Detailed Neutron Dosimetry and Damage Analysis

Ketema, DJ
NRG, Product Group Materials, Monitoring & Inspection,

Pages: 8    Published: Jan 2001

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Source: STP1398-EB

Abstract

This document shows that the combination of 3D neutron transport calculations with the results from activation foil measurements at a limited number of locations in a materials testing irradiation experiment can provide information at any position in the experiment for detailed neutron dosimetry and damage analysis.

Keywords:
activation foils, 3D calculations, MCNP, neutron dosimetry, material damage

Paper ID: STP13602S
Committee/Subcommittee: E10.01
DOI: 10.1520/STP13602S
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