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Title: Evaluation of the thermal-neutron constants for /sup 233/U, /sup 235/U, /sup 239/Pu and /sup 241/Pu

Technical Report ·
DOI:https://doi.org/10.2172/6848400· OSTI ID:6848400

A consistent set of best values of the 2200 meter/second neutron cross sections, Westcott g-factors, and fission neutron yields for /sup 233/U, /sup 235/U, /sup 239/Pu and /sup 241/Pu are presented. A least squares fitting program, LSF, is used to obtain the best fit and to estimate the sensitivity of these fissile parameters to the quoted uncertainties in experimental data. The half-lives of the uranium and plutonium nuclides have been evaluated and these have been used to reassess the significant experimental data. The latest revision of the spontaneous fission neutron yield anti nu, of /sup 252/Cf and the foil thickness corrections to the fission neutron yield ratios of fissile nuclei to /sup 252/Cf are included. These lead to greater consistency in the data used for anti nu (/sup 252/Cf). Similarly, the /sup 234/U half-life as revised leads to improved consistency in the /sup 235/U fission cross section. Comparison is made with the values from ENDF/B-V and other evaluations.

Research Organization:
National Nuclear Data Center, Upton, NY (USA)
DOE Contract Number:
AC02-76CH00016
OSTI ID:
6848400
Report Number(s):
BNL-NCS-31878; CONF-820942-21; ON: DE83000974
Resource Relation:
Conference: Nuclear data for science and technology international conference, Antwerp, Belgium, 6 Sep 1982; Other Information: Portions of document are illegible
Country of Publication:
United States
Language:
English