ENDF/B-IV Thermal Data Testing: Methods, Results, and Recommendations

Conference · Sun Jun 13 04:00:00 EDT 1976

OSTI ID:7347236

McCrosson, F. J. ^[1]

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1. Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.

The Evaluated Nuclear Data File/Library B (ENDF/B) provides a computer-oriented reference set of evaluated neutron cross sections for thermal and fast reactor applications, photon interaction cross sections, and photon production data. The current evaluations span the energy range from 0 to 20 MeV. This paper presents ENDF/B-IV data testing results from seven organizations on seventeen thermal benchmark experiments. Development and testing of ENDF/B-IV is the latest contribution of the Cross Section Evaluation Group. The file is maintained at, and released through, the National Neutron Cross Section Center at Brookhaven National Laboratory. The ENDF/B-IV predictions for uranium systems are an improvement over ENDF/B-III. Recommendations include extending the benchmark experiments to plutonium, urania, thoria, and mixed oxide systems and preparing a revised library, ENDF/B-V.

• 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 Energy Research and Development Administration (ERDA)
• OSTI ID: 7347236
• Report Number(s): DP-MS-76-8; CONF-760622--34
• Country of Publication: United States
• Language: English

Related Subjects

652025* -- Nuclear Properties & Reactions
A=220 & above
Experimental-- Nuclear Reactions & Scattering-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
BARYON REACTIONS
BARYONS
CAPTURE
CROSS SECTIONS
ELEMENTARY PARTICLES
Evaluated Nuclear Data File/Library B (ENDF/B)
FERMIONS
FISSION
HADRON REACTIONS
HADRONS
NEUTRON REACTIONS
NEUTRONS
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
Nuclear Criticality Safety Program (NCSP)
REACTORS
STANDARDS
TARGETS
THERMAL NEUTRONS
THERMAL REACTORS
Thermal Benchmark Experiments
URANIUM 235 TARGET
URANIUM 238 TARGET