SYMPOSIA PAPER Published: 01 January 1963

Fast-Neutron Dosimetry at the MTR-ETR Site


Fast-neutron dosimetry at the Materials Testing Reactor - Engineering Test Reactor (MTR-ETR) Site consists of routine fast-flux measurement and the development of new techniques. The threshold reaction, Ni58n, p)Co58, is being used where the high thermal-neutron cross-sections of the cobalt-58 isomers are not a detriment and the reactions Ti46(n,p)Sc46 and Fe54(n,p)Mn54 are used as alternatives.

In the development program, 14 fast-neutron cross-sections averaged over the fission spectrum in Experimental Breeder Reactor 1 (EBR-I) have been measured relative to the assumed 0.57-mb value for the reaction Al27(n,α)Na24. The reactions investigated and the fast-neutron cross-sections in mb are: Mg24(n, p)Na24, 1.1; Ti46(n, p)Sc46, 9.0; Ti47(n, p)Sc47, 15; Ti48(n, p)Sc48, 0.25; Mn55(n, 2n)Mn54, 0.18; Fe54(n, p)Mn54, 65; Fe56(n, p)Mn56, 0.71; Ni58(n, p)Co58, 90; Ni60(n, p)Co60, >0.5; Cu63(n, α)Co60, 0.42; Zn64(n, p)Cu64, 25; Zn66 (n,2n)-Zn65, >4; Mo92(n, p)Cb92, 6.0; Mo95(n, p)Cb95, >0.1.

Author Information

Hogg, C., H.
Phillips Petroleum Co., Idaho Falls, Idaho
Weber, L., D.
Phillips Petroleum Co., Idaho Falls, Idaho
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Developed by Committee: E10
Pages: 133–140
DOI: 10.1520/STP41747S
ISBN-EB: 978-0-8031-5984-6
ISBN-13: 978-0-8031-6138-2