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NUREG-1537, Part 2 - NRC

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APPIEMDC 18.1<br />

Oak Ridge National Laboratory, ORNL TM-627, T. M Sims and W. X Tabor,<br />

"Report on Fuel-Plate Melting at the Oak Ridge Research Reactor, July 1, 1963,"<br />

October 1964.<br />

Shibata, Toshikazu, et al., 'Release of Fission Products From Irradiated Aluminide<br />

Fuel at High Temperatures" Nuclear &ience andEngineerng 87, pp. 405-417,<br />

1984.<br />

Thompson, T. I., "Accidents and Destructive Tests," The Technology ofNuclear<br />

Reactor Sqfe, MIT Press, 1964.<br />

U.S. Atomic Energy Commission, TID 14844, J. J. Dilunno, "Calculation of<br />

Distance Factors for Power and Test Reactor Sites," March 23, 1961.<br />

U.S. Nuclear Regulatory Commission, NEUREG-0849, 'Standard Review Plan for<br />

Research Reactor Emergency Plans," 1985.<br />

U.S. Nuclear Regulatory Commission, <strong>NUREG</strong>-085 1, "Nomograms for<br />

Evaluation of Doses From Finite Noble Gas Clouds," 1983.<br />

U.S. Nuclear Regulatory Commission, <strong>NUREG</strong>-1281, "Evaluation ofthe<br />

Qualification of SPERT Fuel for Use in Non-Power Reactors," 1987.<br />

U.S. Nuclear Regulatory Commission, <strong>NUREG</strong>-1282, "Safety Evaluation Report<br />

on High-Uranium Content, Low-Enriched Uranium-Zirconium Hydride Fuels for<br />

TRIGA Reactors," 1987.<br />

U.S. Nuclear Regulatory Commission, <strong>NUREG</strong>-13 13, "Safety Evaluation Report<br />

Related to the Evaluation of Low-Enriched Uranium Silicide-Ahminum<br />

Dispersion Fuel for Use in Non-Power Reactors, 1988.<br />

U.S. Nuclear Regulatory Commission, <strong>NUREG</strong>-1478,"Non-Power Reactor<br />

Operator Licensing Exaniner Standards," 1993.<br />

U.S. Nuclear Regulatory Commission, <strong>NUREG</strong>/CR-2079,"Analysis of Credible<br />

Accidents for Argonaut Reactors," April 1981.<br />

U.S. Nuclear Regulatory Commission, <strong>NUREG</strong>/CR-2198, "Fuel Temperatures in<br />

an Argonaut Reactor Core Following a Hypothetical Design Basis Accident<br />

(DBA)," June 1981.<br />

U.S. Nuclear Regulatory Commission, <strong>NUREG</strong>/CR-2387, "Credible Accident<br />

Analyses for TRIGA and TRIGA-fuieled Reactors," April 1982.<br />

NJREG-<strong>1537</strong>,PT2 58 REV. 0, 2i96<br />

<strong>NUREG</strong>-1 537, PART 2 58 REV. 0, 2/96<br />

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