OPAL Reactor: calculation/experiment comparison of neutron flue mapping in fuel coolant channels
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Date
2013-10-13
Journal Title
Journal ISSN
Volume Title
Publisher
International Group On Research Reactors
Abstract
The measurement and calculation of the neutron flux mapping of the OPAL research reactor are presented. Following an investigation of fuel coolant channels using sub-miniature fission chambers to measure thermal neutron flux profiles, neutronic calculations were performed. Comparison between calculation and measurement shows very good agreement. © The Authors
Description
Keywords
Computer calculations, Coolants, Neutron flux, OPAL Reactor, Pool type reactors, Radiation flux, Reactors, Thermal reactors, Water cooled reactors, Neutrons
Citation
Barbot, L., Domergue, C., Villard, J.-F., Destouches, C., Braoudakis, G., Wassink, D., Sinclair, B., Osborn, J. C., & Wu, H. (2013). OPAL Reactor: calculation/experiment comparison of neutron flue mapping in fuel coolant channels. Paper presented at the 15th meeting of the International Group on Research Reactors, "IGORR 15", 13-18 Oct 2013, Daejeon, South Korea, Retrieved from: https://www.igorr.com/Documents/2013-DAEJEON/11_1005.pdf