Fission, Total and Neutron Capture Cross Section Measurements at ORELA for ²³³U, ²⁷A1 and Natural Chlorine

Conference · Mon Oct 05 00:00:00 EDT 1998

OSTI ID:666164

Guber, K. H. ^[1]; Spencer, R. R. ^[1]; Leal, L. C. ^[1]; Larson, D. C. ^[1]; Santos, G. Dos ^[1]; Harvey, J. A. ^[1]; Hill, N. W. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

The authors have made use of the Oak Ridge Electron Linear Accelerator (ORELA) to measure the fission cross section of ²³³U in the neutron energy range of 0.36 eV to ~700 keV. This paper reports integral data and average cross sections. In addition, they measured the total neutron cross section of ²⁷A1 and natural chlorine, as well as the capture cross section of A1 over an energy range from 100 eV up to about 400 keV.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 666164
• Report Number(s): ORNL/CP-98821; CONF-981003-; ON: DE98007157; BR: EW3110059; TRN: 99:000278
• Resource Relation: Conference: International Conference on the Physics of Nuclear Science and Technology, Physor 1998, Long Island, NY (United States), 5-8 Oct 1998; Other Information: PBD: [1998]
• Country of Publication: United States
• Language: English

Related Subjects

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
NEUTRON REACTIONS
FISSION
CAPTURE
TOTAL CROSS SECTIONS
URANIUM 232 TARGET
ALUMINIUM 27 TARGET
CHLORINE
EV RANGE
KEV RANGE
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
Oak Ridge Electron Linear Accelerator (ORELA)
Time-Of-Flight (TOF)
Neutron Source
Fission Chamber
Neutron Transmission