Published May 1987 | Version v1
Journal article

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

Description

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 236U and 237Np irradiated in special ampules. We give the results of measurements of the ratio (σ/sub n,2n/ + σ/sub γ,n/)σ/sub c/ for 237Np 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

Additional details

Publishing Information

Journal Title
Sov. At. Energy (Engl. Transl.)
Journal Volume
61
Journal Issue
5
Series
Sov. At. Energy (Engl. Transl.).
Journal Page Range
973-974
ISSN
0038-531X
CODEN
SATEA

Optional Information

Notes
Translated from At. Ehnerg.; 61: No. 5, 389-390(Nov 1986).