The data base of the standards and related cross sections after ENDF/B-VI

Conference · Thu Dec 31 00:00:00 EST 1992

DOI:https://doi.org/10.2172/6749131· OSTI ID:508116

Poenitz, W P ^[1]; Carlson, A D ^[2]

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1. Argonne National Lab. - West, Idaho Falls, ID (United States)
2. National Institute of Standards and Technology, Washington, DC (United States)

A brief description is given of the procedure used in the global evaluation of the standards and other important cross sections for ENDF/B-VI. The standards involved were {sup 6}Li(n,t), {sup 10}B(n,{alpha}{sub 1}), {sup 197}Au(n,{gamma}), and {sup 235}U(n,f). Other standards evaluated independently were H(n,p), {sup 3}He(n,p), C(n,f). The other cross sections involved were {sup 238}U(n,{gamma}), {sup 238}U(n,f), and {sup 239}Pu(n,f). The results of the evaluation are compared with new or revised experimental data which have become available after the completion of ENDF/B-VI. Overall good agreement is found, but a few problems are indicated by the new data.

• Research Organization: National Inst. of Standards and Technology (NML), Gaithersburg, MD (United States). Radiation Physics Div.
• Sponsoring Organization: USDOE Office of Energy Research, Washington, DC (United States)
• DOE Contract Number: AI05-91ER40610
• OSTI ID: 508116
• Report Number(s): DOE/ER/40610-T3; CONF-9210303-1; ON: DE97007331; TRN: 97:013406
• Resource Relation: Conference: International symposium on Nuclear Data Evaluation Methodology, Brookhaven, NY (United States), 12-16 Oct 1992; Other Information: PBD: 1992
• Country of Publication: United States
• Language: English

Related Subjects

66 PHYSICS
NUCLEAR DATA COLLECTIONS
DATA BASE MANAGEMENT
NEUTRON REACTIONS
CROSS SECTIONS
CAPTURE
URANIUM ISOTOPES
PLUTONIUM 239 TARGET
BORON ISOTOPES
LITHIUM 6 TARGET
GOLD 197 TARGET
HYDROGEN 1 TARGET
HELIUM 3 TARGET
CARBON 12 TARGET