Thermal Data Testing of ENDF/B-III and Prognosis for ENDF/B-IV
Conference
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OSTI ID:4297366
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.
One of the activities of the ENDF/B Cross Section Evaluation working Group (CSEWG) is testing differential ENDF/B cross sections ill integral benchmark experiments. In this paper, I will be presenting the ENDF/B-III data testing results as obtained by the CSEWG Data 'Testing Subcommittee. These results have provided a) a basis for evaluating the merit of ENDF/B-I11 in the analysis of thermal systems, and b) a reference to assist evaluators in the development of improved thermal neutron data for ENDF/B-IV.
- Research Organization:
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-30-017897
- OSTI ID:
- 4297366
- Report Number(s):
- DP-MS--74-14; CONF-740608--13
- Country of Publication:
- United States
- Language:
- English
Similar Records
ENDF/B-IV Thermal Data Testing: Methods, Results, and Recommendations
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ZPR-III Assembly 48 GAFGAR ENDF/B Data Tapes; ZPR-III assembly 48 GAFGAR ENDF/B data tapes. [UNIVAC1108; Variable-length binary records]
Conference
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Sun Jun 13 00:00:00 EDT 1976
·
OSTI ID:7347236
Activities of the Shielding Subcommittee of the ENDF/B Cross Section Evaluation Working Group
Conference
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Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:7218286
ZPR-III Assembly 48 GAFGAR ENDF/B Data Tapes; ZPR-III assembly 48 GAFGAR ENDF/B data tapes. [UNIVAC1108; Variable-length binary records]
Technical Report
·
·
OSTI ID:6343478
Related Subjects
*NUCLEAR DATA COLLECTIONS
*PLUTONIUM NITRATES-- CRITICALITY
*REACTOR LATTICE PARAMETERS
*URANYL NITRATES-- CRITICALITY
22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
CROSS SECTIONS
Data Testing Results
ENDF/B Cross Section Evaluation working Group (CSEWG)
NEUTRON REACTIONS
Nuclear Criticality Safety Program (NCSP)
URANIUM
*PLUTONIUM NITRATES-- CRITICALITY
*REACTOR LATTICE PARAMETERS
*URANYL NITRATES-- CRITICALITY
22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
CROSS SECTIONS
Data Testing Results
ENDF/B Cross Section Evaluation working Group (CSEWG)
NEUTRON REACTIONS
Nuclear Criticality Safety Program (NCSP)
URANIUM