EFFECTIVE NEUTRON REMOVAL CROSS SECTIONS FOR CARBON AND OXYGEN IN CONTINUOUS MEDIUMS
ABS>An expanded version of a paper previously published in ORNL-2051, p.157 (1956). Thermal-neutron flux measurements at the Lid Tank Shielding Facility in water, oil, and a sugar--water solution have been used to calculate effective neutron removal cross-section values of carbon and oxygen distributed in continuous media. The values are 0.72 plus or minus 0.05 barn for carbon and 0.92 plus or minus 0.05 barn for oxygen. These values are somewhat lower than previously reported values determined by another method, but the differences may be attributable to experimental errors. (auth)
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-12-016621
- OSTI ID:
- 4297657
- Report Number(s):
- ORNL-2197
- Resource Relation:
- Other Information: An expanded version of a paper previously published in ORNL-2081, p.167 (1956). Orig. Receipt Date: 31-DEC-58
- Country of Publication:
- United States
- Language:
- English
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