CALCULATION AND COMPARISONS WITH MEASUREMENT OF FAST NEUTRON FLUXES IN THE MATERIAL TESTING FACILITIES OF THE NRU RESEARCH REACTOR
33rd Annual CNS Conference - 2012 June 10-13


Presented at:
33rd Annual CNS Conference
2012 June 10-13
Location:
Saskatoon, Canada
Session Title:
Physics-1

Authors:
Timothy Leung (Atomic Energy of Canada Limited)
  

Abstract

The NRU reactor at Chalk River provides three irradiation facilities to study the effects of fast neutrons (E> 1 MeV) on reactor materials for assessing material damages and deformations. The facilities comprise two types of fast neutron rods (Mark-4 and Mark-7), and one type of Material Test Bundles (MTB). This paper describes the neutronic simulations in these facilities using the WIMS-AECL and TRIAD code, and comparisons with the fast neutron flux measurements using iron-wire activation techniques. It also provides the comparisons of flux levels, neutron spectra, and the size limitations of the experimental cavities between these facilities.

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