NUREG-1537, Part 2 - NRC

CHAPShR 13
U.S. Nuclear Regulatory Commission, Safety Evaluation Report on High-Uraniun)
Content. Low-Enriched Uranium-Zirconium Hydride Fuels for TRIGA Reactors,
NUREG-1282, 1987.
West, G. B., et al., 'Kinetic Behavior of TRIGA Reactors," GA-7882, General
Atomics Company, March 1967.
Behavior of Plate Fueled Reactors (MTR)
Bullock, J. B., "Calculation of Maximum Fuel Cladding Temperatures for Two
Megawatt Operation of the Ford Nuclear Reactor," Memorandum Report No. 1,
Memorial Phoenix Project, Michigan, June 1962.
Forbes, S. G., et al., Instability in the SPERT I Reactor. Preliminary Report. IDO-
16309, Idaho Operations Office, Atomic Energy Commission, Idaho Falls, ID,
October 1956.
Knexevich, M., et al., -Loss of Water at the Livermore Pool Type Reactor,"
Health Physics IL 1965, pp. 481-487.
Miller, R. N., et al., Report of the SPERT I Destructive Test Program on an
Aluminum. Plate-Tvve. Water-Moderated Reactor. ID0-16883, Idaho Operations
Office, Atomic Energy Commission, Idaho Falls, ID, June 1964.
Nyer, W. E., et al, Experimental Investigations of Reactor Transients.
IDO-16285, Idaho Operations Office, Atomic Energy Commission, Idaho Falls,
ID, April 1956.
Shibata, T., et al., "Release of Fission Products from Irradiated Aluminide Fuel at
High Temperatures," Nuclear Science and Engineering 87. 1984, pp. 405-417.
Sims, T. M, and Tabor, W. H., Revort on Fuel-Plate Melting at the Oak Ridge
Research Reactor. July 1. 1963. ORN-TM-627, Oak Ridge National Laboratory,
October 1964.
Wett, J. F., Jr., Surface Temperatures of Irradiated ORR Fuel Elements Cooled in
Stagnant Air, ORNL-2892, Oak RidgeNational Laboratory, April 16, 1960.
U.S. Nuclear Regulatory Commnission, "Analysis of Credible Accidents for
Argonaut Reactors," NUREGICR-2079, Pacific Northwest Laboratories, April
1981.
U.S. Nuclear Regulatory Commission, Rubenstein, L. S., memo to Tedesco, R. L.,
"Design Basis Event for the University of Michigan Reactor," June 17, 1981.
NUREG-1537, PMT2 13-16 REV 0,2/96
NUTREG-1537, PART2 13-16 REV 0, 2/96
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