Abstract
Irradiation in a light water reactor involves varying neutron intensity levels. The calculation of neutron flux density is based on the assumption that the neutron intensity is proportional to the reactor thermal power. Ideally, the total irradiation time should be broken down into periods of uniform thermal power levels; however, analysts use approximations such as average power during operating periods between shutdowns, or monthly average power.
This study compares the values of A/As obtained with several commonly-used averaging methods, such as those mentioned above with that obtained using a daily thermal power generation history. All calculations will be made using actual light water reactor operating histories for several of the common dosimeter materials.
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References
Title 10, Code of Federal Regulations, Part 50, ″Licensing of Production and Utilization Facilities,″ 1983 Revision.
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© 1985 ECSC, EEC, EAEC, Brussels and Luxembourg
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Norris, E.B. (1985). Effect of Thermal Power Averaging Method on the Determination of Neutron Fluence for LWR-PV Surveillance. In: Genthon, J.P., Röttger, H. (eds) Reactor Dosimetry. Springer, Dordrecht. https://doi.org/10.1007/978-94-009-5378-9_12
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DOI: https://doi.org/10.1007/978-94-009-5378-9_12
Publisher Name: Springer, Dordrecht
Print ISBN: 978-94-010-8873-2
Online ISBN: 978-94-009-5378-9
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