Published 2009 | Version v1
Miscellaneous

Neutronic modeling and thermal neutron flux measurement of the MCR6 rod in the NRU reactor

  • 1. Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

Description

The six-barrel Multiple-Capsule Water Cooled Rods (MCR6) in the NRU reactor have been used to produce isotopes such as I-131 and Ir-192. This paper describes the modeling of the MCR6 rods and the simulation method used to predict the neutron fluxes. The sensitivity of various radioisotope loadings of MCR6 rods upon flux and power perturbations of neighbouring rods is investigated. This paper also presents the results of thermal neutron flux measurements in one of the MCR6 rods from gold wire detectors using the neutron activation technique. The measured fluxes match very well with the simulated fluxes, within ±2%. (author)

Part of:
New nuclear frontiers. 30th annual Canadian Nuclear Society conference and 33rd CNS/CNA student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-95-X
Imprint Title
New nuclear frontiers. 30th annual Canadian Nuclear Society conference and 33rd CNS/CNA student conference
Imprint Pagination
275 Megabytes
Journal Page Range
[12 p.]

Conference

Title
30. annual canadian nuclear society conference; 33. CNS/CNA student conference
Dates
31 May - 3 Jun 2009
Place
Calgary, Alberta (Canada)

Optional Information

Notes
6 refs., 4 tabs., 4 figs.