ORIGEN sample problem using fission product file derived from ENDF/B-IV fission product decay data
The ORIGEN code solves the equations of radioactive growth and decay; it allows continuous first-order chemical processing and a neutron flux described by a three-region spectrum. Complex decay and transmutation schemes can be treated. This user's manual contains some informal notes on the ORIGEN code; a copy of ORNL-4628, which describes the code and its use; and a library of ORIGEN yields and cross sections, with accompanying notes. (RWR)
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5035630
- Report Number(s):
- CCC-217; TRN: 78-008825
- Country of Publication:
- United States
- Language:
- English
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Application of a library of processed ENDF/B-IV fission-product aggregate decay data in the calculation of decay-energy spectra. [FITPULS, in FORTRAN for CDC computers]
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Thu Jan 01 00:00:00 EST 1976
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OSTI ID:5035630
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Thu May 01 00:00:00 EDT 1980
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Application of a library of processed ENDF/B-IV fission-product aggregate decay data in the calculation of decay-energy spectra. [FITPULS, in FORTRAN for CDC computers]
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OSTI ID:5035630
+1 more
Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPUTER CODES
O CODES
FISSION PRODUCTS
DECAY
RADIOISOTOPES
BURNUP
CROSS SECTIONS
DAUGHTER PRODUCTS
DOCUMENTATION
FUEL CANS
GAMMA SPECTRA
ISOTOPE RATIO
MATHEMATICAL MODELS
NUCLEAR FUELS
NUCLEAR REACTION YIELD
RADIOACTIVITY
SPENT FUELS
ENERGY SOURCES
FUELS
ISOTOPES
RADIOACTIVE MATERIALS
REACTOR MATERIALS
SPECTRA
YIELDS
652026* - Nuclear Properties & Reactions
A=220 & above
Experimental- Spontaneous & Induced Fission- (-1987)
220100 - Nuclear Reactor Technology- Theory & Calculation
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPUTER CODES
O CODES
FISSION PRODUCTS
DECAY
RADIOISOTOPES
BURNUP
CROSS SECTIONS
DAUGHTER PRODUCTS
DOCUMENTATION
FUEL CANS
GAMMA SPECTRA
ISOTOPE RATIO
MATHEMATICAL MODELS
NUCLEAR FUELS
NUCLEAR REACTION YIELD
RADIOACTIVITY
SPENT FUELS
ENERGY SOURCES
FUELS
ISOTOPES
RADIOACTIVE MATERIALS
REACTOR MATERIALS
SPECTRA
YIELDS
652026* - Nuclear Properties & Reactions
A=220 & above
Experimental- Spontaneous & Induced Fission- (-1987)
220100 - Nuclear Reactor Technology- Theory & Calculation