Measurements of Neutron Induced Cross Sections at the Oak Ridge Electron Linear Accelerator

Conference · Mon Sep 20 00:00:00 EDT 1999

OSTI ID:6919

Guber, K. H. ^[1]; Spencer, R. R. ^[1]; Leal, L. C. ^[1]; Koehler, P. E. ^[1]; Sayer, R. O. ^[1]; Harvey, J. A. ^[1]; Hill, N. W. ^[1]

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

We have used the Oak Ridge Electron Linear Accelerator (ORELA) to measure neutron total and the fission cross sections of ²³³U in the energy range from 0.36 eV to ~700 keV. We report average fission and total cross sections. Also, we measured the neutron total cross sections of ²⁷Al and Natural chlorine as well as the capture cross section of Al 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 National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Environmental Management (EM)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 6919
• Report Number(s): ORNL/CP-102969; ON: DE00006919
• Resource Relation: Conference: ICNC '99: 6. International Conference on Nuclear Criticality Safety, Palais des Congres, Versailles (France), 20-24 Sep 1999
• 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
Cross Sections
ORELA
Nuclear Criticality Safety Program (NCSP)
Oak Ridge Electron Linear Accelerator (ORELA)
Neutron Energy Range
Neutron Capture Measurements
Black Resonance Technique
Data Aquisition Electronics
SAMMY
Evaluated Nuclear Data File (ENDF)
JENDL 3.2