The simultaneous evaluation of the standards and other cross sections of importance for technology
The simultaneous evaluation of the cross sections of {sup 6}Li(n,{alpha}), {sup 6}Li(n,n), {sup 10}B(n,{alpha}{sub 0}), {sup 10}B(n,{alpha}{sup 1}), {sup 10}B(n,n), {sup 197}Au(n,{gamma}), {sup 238}U(n,{gamma}), {sup 235}U(n,f), {sup 239}Pu(n,f), and {sup 238}U(n,f) and the thermal constants was part of the evaluation of these data for ENDF/B-VI The FORTRAN codes and the data files used for the simultaneous evaluation are documented in the present report. Corrections for some data reported in the literature and the addition of several new data sets results in negligible changes except for the fission cross sections where minor changes occur relative to the evaluation for ENDF/B-VI.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Energy Research, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 658382
- Report Number(s):
- ANL/NDM-139; ON: DE98004912; TRN: 98:011136
- Resource Relation:
- Other Information: PBD: Sep 1997
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
66 PHYSICS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
EVALUATION
CROSS SECTIONS
NEUTRON REACTIONS
LITHIUM 6 TARGET
BORON 10 TARGET
GOLD 197 TARGET
URANIUM 238 TARGET
PLUTONIUM 239 TARGET
URANIUM 235 TARGET
CAPTURE
FISSION
NUCLEAR DATA COLLECTIONS
ELASTIC SCATTERING
TRANSFER REACTIONS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
EVALUATION
CROSS SECTIONS
NEUTRON REACTIONS
LITHIUM 6 TARGET
BORON 10 TARGET
GOLD 197 TARGET
URANIUM 238 TARGET
PLUTONIUM 239 TARGET
URANIUM 235 TARGET
CAPTURE
FISSION
NUCLEAR DATA COLLECTIONS
ELASTIC SCATTERING
TRANSFER REACTIONS