Revised evaluations for ENDF/B-VI revision
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5874509
- Oak Ridge National Lab., TN (United States)
This paper reports on revised cross-section evaluations for 17 nuclides that have been prepared for ENDF/B-VI, Revision 2. The nuclides considered include five fission products and various isotopes of cadmium and hafnium. The previous ENDF/B-VI evaluations for these 17 nuclides were carried over from ENDF/B-V and were completed in the 1974-1980 time period. By utilizing the experimental data that have become available since 1980, the revised evaluations will result in significant improvements in the evaluated nuclear data files. The primary emphasis was placed on the resolved and unresolved resonance regions, but new experimental data were also used to improve the cross sections for energies above the unresolved resonance region. Negative elastic-scattering cross sections were encountered in some of the previous evaluations; because the revised evaluations use multilevel Breit-Wigner parameters, rather than single-level Breit-Wigner, this problem is eliminated.
- OSTI ID:
- 5874509
- Report Number(s):
- CONF-930601--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 68
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
663610* -- Neutron Physics-- (1992-)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CADMIUM
CALCULATION METHODS
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
ELEMENTS
HAFNIUM
METALS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROGRAMMING
R CODES
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR CORES
SIMULATION
THERMAL POWER PLANTS
TRANSITION ELEMENTS
VECTOR PROCESSING
220100 -- Nuclear Reactor Technology-- Theory & Calculation
663610* -- Neutron Physics-- (1992-)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CADMIUM
CALCULATION METHODS
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
ELEMENTS
HAFNIUM
METALS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROGRAMMING
R CODES
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR CORES
SIMULATION
THERMAL POWER PLANTS
TRANSITION ELEMENTS
VECTOR PROCESSING