ENDF/B-5 fission product cross section evaluations [electronic resource]

Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files. Most of the evaluations involve updating the capture cross sections of the important absorbers for fast and thermal reactor systems. This included updating thermal values, resonance integrals, resona...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Hanford Engineering Development Laboratory (Researcher), Hanford Site (Wash.) (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Richland, Wash. : Oak Ridge, Tenn. : Hanford Site (Wash.) ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1979.
Subjects:

MARC

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245 0 0 |a ENDF/B-5 fission product cross section evaluations  |h [electronic resource] 
260 |a Richland, Wash. :  |b Hanford Site (Wash.) ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,  |c 1979. 
300 |a Pages: 33 :  |b digital, PDF file. 
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500 |a Published through SciTech Connect. 
500 |a 12/01/1979. 
500 |a "hedl-sa-1969-fp" 
500 |a " conf-791223-3" 
500 |a NEANDC specialist meeting on neutron cross sections of fission product nuclei, Bologna, Italy, 12 Dec 1979. 
500 |a Schenter, R.E.; England, T.R. 
520 3 |a Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files. Most of the evaluations involve updating the capture cross sections of the important absorbers for fast and thermal reactor systems. This included updating thermal values, resonance integrals, resonance parameter sets, and fast capture cross sections. For the fast capture results generalized least-squares calculations were made with the computer code FERRET. Input for these cross section adjustments included nuclear models calculations and both integral and differential experimental data results. The differential cross sections and their uncertainties were obtained from the CSIRS library. Integral measurement results came from CFRMF and STEK Assemblies 500, 1000, 2000, 3000, 4000. Comparisons of these evaluations with recent capture measurements are shown. 15 figures, 10 tables. 
536 |b EY-76-C-14-2170. 
650 7 |a Information.  |2 local. 
650 7 |a Neutrons.  |2 local. 
650 7 |a Elementary Particles.  |2 local. 
650 7 |a Least Square Fit.  |2 local. 
650 7 |a Numerical Solution.  |2 local. 
650 7 |a Fast Neutrons.  |2 local. 
650 7 |a Baryon Reactions.  |2 local. 
650 7 |a Nucleons.  |2 local. 
650 7 |a Integrals.  |2 local. 
650 7 |a Isotopes.  |2 local. 
650 7 |a Hadron Reactions.  |2 local. 
650 7 |a Evaluated Data.  |2 local. 
650 7 |a Neutron Reactions.  |2 local. 
650 7 |a Baryons.  |2 local. 
650 7 |a Fermions.  |2 local. 
650 7 |a Tables.  |2 local. 
650 7 |a Data Forms.  |2 local. 
650 7 |a Cross Sections.  |2 local. 
650 7 |a Nuclear Reactions.  |2 local. 
650 7 |a Numerical Data.  |2 local. 
650 7 |a Thermal Neutrons.  |2 local. 
650 7 |a Graphs.  |2 local. 
650 7 |a Nucleon Reactions.  |2 local. 
650 7 |a Burnup.  |2 local. 
650 7 |a Hadrons.  |2 local. 
650 7 |a Capture.  |2 local. 
650 7 |a Resonance Integrals.  |2 local. 
650 7 |a Data.  |2 local. 
650 7 |a Radioactive Materials.  |2 local. 
650 7 |a Nuclear Data Collections.  |2 local. 
650 7 |a Maximum-likelihood Fit.  |2 local. 
650 7 |a Fission Products.  |2 local. 
650 7 |a Nuclear Physics And Radiation Physics.  |2 edbsc. 
710 2 |a Hanford Engineering Development Laboratory.  |4 res. 
710 2 |a Hanford Site (Wash.).  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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