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Title: DISPERSION OF THE NEUTRON EMISSION IN U$sup 235$ FISSION

Abstract

Equations are developed which allow the calculation of the average number of neutrons per U{sup 235} fission from experimental measurements. Experimental methods are described, the results of which give a value of (7.8{+-}0.6){sup 1/2} neutrons per U{sup 235} thermal fission. (D.E.B.)

Authors:
; ;
Publication Date:
Research Org.:
Los Alamos Scientific Lab., N. Mex. (US)
Sponsoring Org.:
US Atomic Energy Commission (AEC) (US)
OSTI Identifier:
4354998
Report Number(s):
AECD-4223
TRN: US200506%%314
DOE Contract Number:  
W-7405-ENG-36
Resource Type:
Technical Report
Resource Relation:
Other Information: Decl. July 15, 1955; PBD: 1 Jan 1955
Country of Publication:
United States
Language:
English
Subject:
72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS; NEUTRON EMISSION; NEUTRONS; THERMAL FISSION; EQUATIONS; FISSION; FISSION PRODUCTS; DATA; NEUTRON SOURCES; THERMAL FISSION FACTOR; URANIUM 235

Citation Formats

Feynman, R.P., de Hoffmann, F., and Serber, R. DISPERSION OF THE NEUTRON EMISSION IN U$sup 235$ FISSION. United States: N. p., 1955. Web. doi:10.2172/4354998.
Feynman, R.P., de Hoffmann, F., & Serber, R. DISPERSION OF THE NEUTRON EMISSION IN U$sup 235$ FISSION. United States. doi:10.2172/4354998.
Feynman, R.P., de Hoffmann, F., and Serber, R. Sat . "DISPERSION OF THE NEUTRON EMISSION IN U$sup 235$ FISSION". United States. doi:10.2172/4354998. https://www.osti.gov/servlets/purl/4354998.
@article{osti_4354998,
title = {DISPERSION OF THE NEUTRON EMISSION IN U$sup 235$ FISSION},
author = {Feynman, R.P. and de Hoffmann, F. and Serber, R.},
abstractNote = {Equations are developed which allow the calculation of the average number of neutrons per U{sup 235} fission from experimental measurements. Experimental methods are described, the results of which give a value of (7.8{+-}0.6){sup 1/2} neutrons per U{sup 235} thermal fission. (D.E.B.)},
doi = {10.2172/4354998},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1955},
month = {1}
}