1. Evaluated Nuclear Data File, B format, distributed within sponsor constraints by National Nuclear Data Center, Brookhaven National Laboratory, Upton, New York. See ENDF/B-V, Brookhaven National Laboratory Report BNL-17541 (ENDF-201), Second Edition (D. Garber, Editor), July, 1979.
2. de Saussure, G. and Perez, R. B., “Representation of the Neutron Cross-Sections in the Unresolved Resonance Region,” in Proceedings of Conference on Nuclear Cross-Sections and Technology, National Bureau of Standards Report NBS-SP-425, Volume 1, Pages 371–374, 1975.
3. Peelle, R. W., “Requirements on Experiment Reporting to Meet Evaluation Needs,” Proceedings of NEANDC/NEACRP Specialists Meeting on Fast Neutron Fission Cross-Sections of U-233, U-235, U-238, and Pu-239, Argonne National Laboratory Report ANL-76-90, ERDA-NDC-5/L, NEANDC(US)-199/L, Pages 421–429, June 28–30, 1976.
4. Perey, F. G., “Covariance Matrices of Experimental Data,” Proceedings of International Conference on Neutron Physics and Nuclear Data for Reactors and Other Applied Purposes, Harwell, United Kingdom, Page 104, September, 1978.
5. Poenitz, W. P., “Interpretaton and Intercomparison of Standard Cross-Sections,” Neutron Standards and Flux Normalization, A. B. Smith, Coordinator, CONF-701002, Page 331, 1970. Kiefhaber, E., “Evaluation of Integral Physics Experiments in Fast Zero Power Facilities,” Section II, Advances in Nuclear Science and Technology, E. J. Henley and J. Lewins, Editors, Volume 8, Pages 47-113, Academic Press, New York, 1975.