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Thermal Neutron Capture Cross Section of Carbon-13
Phys. Rev. 95, 92 – Published 1 July, 1954
DOI: https://doi.org/10.1103/PhysRev.95.92
Abstract
The thermal neutron capture cross section of has been determined from the amount of formed in pile-irradiated samples of graphite, barium carbonate, and carbon dioxide. Because of the impurity reaction, , of comparatively high cross section, the results were consistent only when samples were used which were enriched in .
The average isotopic cross section determined for the enriched samples was 1.4±0.2 millibarns. The final value of the cross section in these samples corrected for the estimated residual nitrogen impurity is 0.9±0.2 millibarn.
References (6)
- National Bureau of Standards Nuclear Data Group, Natl. Bur. Standards (U. S.) Circ. No. 499 (U. S. Government Printing Office, Washington, D. C., 1950)
- [D. J. Hughes et al., U. S. Atomic Energy Commission Report AECU-2040 (Technical Information Service, Department of Commerce, Washington, D. C., 1952).] reported by the author in an Argonne National Laboratory Report ANL-4345, October 11, 1949 (unpublished)
- Anderson, Libby, Weinhouse, Reid, Kirschenbaum, and Grosse, Science 105, 576 (1947)
- G. R. Hennig, Argonne National Laboratory Report ANL-4080, January, 1948 (unpublished)
Omitted endnote
- C. L. Mantell, Industrial Carbon (D. Van Nostrand Company, Inc. New York, 1946), p. 361