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Fuel fragmentation, relocation, and dispersal during the loss-of-coolant accident
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The gentle killers
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APWR no daihadan LOCA kaiseki no kentō
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TRAC-M/FORTRAN 90 (version 3.0) user manual
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An evaluation of fuel fabrication and the back end of the fuel cycle for light-water-and heavy-water-cooled nuclear power reactors
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Proceedings of the Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
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Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
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Development and validation of a transition boiling model for the RELAP5/MOD3 reflood simulation
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Proceedings of the Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
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Cladding swelling and rupture models for LOCA analysis
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Analysis and proposed revision of the radiation protection and waste management programs as described in the Oregon State University TRIGA research reactor safety analysis report
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Development of the LOFT prototype drag screen
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Proceedings
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Review of organic iodide formation under accident conditions in water-cooled reactors
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TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6
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The temperature dependence of G-values for aqueous solutions irradiated with a 23 MeV 2H+ beam
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Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2
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Review of Fuel Failures in Water Cooled Reactors (Technical Reports Series (International Atomic Energy Agency))
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Water Chemistry of Nuclear Reactor Systems 3 (Water Chemistry of Nuclear Reactor Systems)
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Properties of light water reactor spent fuel cladding
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Sensitivity study of the DEG LBLOCA transient on the counter-current flow limitation by using TRACE
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TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6
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Xerox Corporation, Webster, New York
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Review of fuel element developments for water cooled nuclear power reactors
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