1980•University of North Texas Digital Library (University of North Texas)Open access

Neutron and gamma characterization within the FFTF reactor cavity

W.L. Bunch, L.L. Carter, F.S. Moore, E. Werner, A.D. Wilcox, Matthew R. Wood

Abstract

Neutron and gamma ray measurements were made within the reactor cavity of the Fast Flux Test Facility (FFTF) to establish the operating characteristics of the Ex-Vessel Flux Monitoring (EVFM) system as a function of reactor power level. A significant effort was made to obtain absolute flux values in order that the measurements could be compared directly with shield design calculations. Good agreement was achieved for neutrons and for both the prompt and delayed components of the gamma ray field. 8 figures, 3 tables.

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Key concepts: Neutron flux, Nuclear engineering, Neutron, Flux (metallurgy), Shield, Research reactor, Reactor pressure vessel, Nuclear physics