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Title: REACTOR NEUTRON CROSS SECTIONS IN FINE ENERGY DETAIL

Abstract

References to the data and a brief resume of the methods used in generating cross sections stored on magnetic tapes in fine energy detail are given. The data are used directly in bare, homogeneous reactor slowing-down calculations or can be processed to provide multi-group of multi-level cross sections in coarser energy detail for other machine programs. Cross sections for 33 elements or isotopes, the U/35 prompt and total fission spectra, and the Be(n,2n) transfer cross sections are currently available. (auth)

Authors:
; ;
Publication Date:
Research Org.:
General Electric Co. Flight Propulsion Lab. Dept., Cincinnati
OSTI Identifier:
4792205
Report Number(s):
APEX-704
NSA Number:
NSA-16-010946
DOE Contract Number:  
AF33(600)-38062; AND AT(11-1)-171
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
PHYSICS; BERYLLIUM; BIBLIOGRAPHY; COMPUTERS; CROSS SECTIONS; ELEMENTS; ENERGY; ENERGY LEVELS; FISSION; GROUP THEORY; HOMOGENEOUS REACTORS; ISOTOPES; NEUTRONS; NUMERICALS; PROGRAMMING; REACTORS; RECORDING SYSTEMS; SLOWDOWN; SPECTRA; URANIUM 235

Citation Formats

Cooper, J.R., Sullivan, R.E., and Henderson, W.B. REACTOR NEUTRON CROSS SECTIONS IN FINE ENERGY DETAIL. United States: N. p., 1961. Web. doi:10.2172/4792205.
Cooper, J.R., Sullivan, R.E., & Henderson, W.B. REACTOR NEUTRON CROSS SECTIONS IN FINE ENERGY DETAIL. United States. doi:10.2172/4792205.
Cooper, J.R., Sullivan, R.E., and Henderson, W.B. Thu . "REACTOR NEUTRON CROSS SECTIONS IN FINE ENERGY DETAIL". United States. doi:10.2172/4792205. https://www.osti.gov/servlets/purl/4792205.
@article{osti_4792205,
title = {REACTOR NEUTRON CROSS SECTIONS IN FINE ENERGY DETAIL},
author = {Cooper, J.R. and Sullivan, R.E. and Henderson, W.B.},
abstractNote = {References to the data and a brief resume of the methods used in generating cross sections stored on magnetic tapes in fine energy detail are given. The data are used directly in bare, homogeneous reactor slowing-down calculations or can be processed to provide multi-group of multi-level cross sections in coarser energy detail for other machine programs. Cross sections for 33 elements or isotopes, the U/35 prompt and total fission spectra, and the Be(n,2n) transfer cross sections are currently available. (auth)},
doi = {10.2172/4792205},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {4}
}