Program RECENT (version 79-1): reconstruction of energy-dependent neutron cross sections from resonance parameters in the ENDF/B format. [In FORTRAN IV for CDC-7600 and Cray-1]
Program RECENT reconstructs energy-dependent neutron total, elastic, capture, and fission cross sections from a combination of resonance parameters and tabulated background cross sections in the ENDF/B format. Entire evaluations, not just cross sections, are written to the result file, which is in ENDF/B format. The output includes the original resonance parameters in a form that can be used in Doppler broadening and self-shielding calculations. A listing of the source deck is available on request. 5 figures, 5 tables.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 5361174
- Report Number(s):
- UCRL-50400(Vol.17)(Pt.C); TRN: 80-009087
- Country of Publication:
- United States
- Language:
- English
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Program SIGMA1 (version 79-1): Doppler broaden evaluated cross sections in the evaluated nuclear data file/version B (ENDF/B) format
Integrated system for production of neutronics and photonics calculational constants. Volume 17, Part B, Rev. 1. Program SIGMA 1 (Version 78-1): Doppler broadened evaluated cross sections in the evaluated nuclear data file/Version B (ENDF/B) format. [For CDC-7600]
Integrated system for production of neutronics and photonics calculational constants. Volume 21, Part C, Program SIGMAL (version 79-1): Doppler-broaden evaluated cross sections in the Livermore-Evaluated Nuclear Data Library (ENDL) format. [In FORTRAN IV for CDC 7600]
Technical Report
·
Wed Oct 31 00:00:00 EST 1979
·
OSTI ID:5361174
Integrated system for production of neutronics and photonics calculational constants. Volume 17, Part B, Rev. 1. Program SIGMA 1 (Version 78-1): Doppler broadened evaluated cross sections in the evaluated nuclear data file/Version B (ENDF/B) format. [For CDC-7600]
Technical Report
·
Tue Jul 04 00:00:00 EDT 1978
·
OSTI ID:5361174
Integrated system for production of neutronics and photonics calculational constants. Volume 21, Part C, Program SIGMAL (version 79-1): Doppler-broaden evaluated cross sections in the Livermore-Evaluated Nuclear Data Library (ENDL) format. [In FORTRAN IV for CDC 7600]
Technical Report
·
Sat Mar 17 00:00:00 EST 1979
·
OSTI ID:5361174
Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTER CODES
R CODES
NEUTRON REACTIONS
CROSS SECTIONS
CAPTURE
CDC COMPUTERS
CRAY COMPUTERS
ELASTIC SCATTERING
ENERGY DEPENDENCE
FISSION
FORTRAN
INTERPOLATION
RESONANCE
TOTAL CROSS SECTIONS
BARYON REACTIONS
COMPUTERS
HADRON REACTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL SOLUTION
PROGRAMMING LANGUAGES
SCATTERING
651000* - Nuclear Physics
654003 - Radiation & Shielding Physics- Neutron Interactions with Matter
COMPUTER CODES
R CODES
NEUTRON REACTIONS
CROSS SECTIONS
CAPTURE
CDC COMPUTERS
CRAY COMPUTERS
ELASTIC SCATTERING
ENERGY DEPENDENCE
FISSION
FORTRAN
INTERPOLATION
RESONANCE
TOTAL CROSS SECTIONS
BARYON REACTIONS
COMPUTERS
HADRON REACTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL SOLUTION
PROGRAMMING LANGUAGES
SCATTERING
651000* - Nuclear Physics
654003 - Radiation & Shielding Physics- Neutron Interactions with Matter