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Title: Determination of the /sup 237/Np(n, 2n) reaction cross section in the core of the BN-350 reactor

Journal Article · · Sov. At. Energy (Engl. Transl.); (United States)
OSTI ID:5328071

Analysis of irradiated fuel (regular fuel elements and special ampule samples) makes it possible to obtain data on the neutron-physical characteristics that do not lend themselves to measurement in experiments with a low neutron flux. The authors studied samples of spent fuel from regular fuel elements and samples of /sup 236/U and /sup 237/Np irradiated in special ampules. We give the results of measurements of the ratio (sigma/sub n,2n/ + sigma/sub ..gamma..,n/)sigma/sub c/ for /sup 237/Np in different zones of the BN-350 reactor and the results of calculations performed using the neptunium group constants calculated from the data of the files ENDFB IV and ENDFB V

OSTI ID:
5328071
Journal Information:
Sov. At. Energy (Engl. Transl.); (United States), Vol. 61:5; Other Information: Translated from At. Ehnerg.; 61: No. 5, 389-390(Nov 1986)
Country of Publication:
United States
Language:
English

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