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Thermal Neutron Capture Cross Section of Carbon-13

G. R. Hennig

  • Chemistry Division, Argonne National Laboratory, Lemont, Illinois

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 C13 has been determined from the amount of C14 formed in pile-irradiated samples of graphite, barium carbonate, and carbon dioxide. Because of the impurity reaction, N14(n, p)C14, of comparatively high cross section, the results were consistent only when samples were used which were enriched in C13.

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)

  1. National Bureau of Standards Nuclear Data Group, Natl. Bur. Standards (U. S.) Circ. No. 499 (U. S. Government Printing Office, Washington, D. C., 1950)
  2. [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 reported by the author in an Argonne National Laboratory Report ANL-4345, October 11, 1949 (unpublished)
  3. Anderson, Libby, Weinhouse, Reid, Kirschenbaum, and Grosse, Science 105, 576 (1947)
  4. G. R. Hennig, Argonne National Laboratory Report ANL-4080, January, 1948 (unpublished)
  5. Omitted endnote

  6. C. L. Mantell, Industrial Carbon (D. Van Nostrand Company, Inc. New York, 1946), p. 361

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