E 1.99:conf-840604-13
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Tensile properties and swelling of 20%-cold-worked Type 316 stainless steel irradiated in HFIR |
1 |
E 1.99: conf-840604-20
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Effects of irradiation fluence and creep on fracture toughness of 347/348 stainless steel |
1 |
E 1.99: conf-840604-21
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Radiation effects on resins and zeolites at Three Mile Island Unit II |
1 |
E 1.99:conf-840604-23
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Experimental determination of the critical cavity radius in Fe-10% Cr for ion irradiation |
1 |
E 1.99: conf-840604-38
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Swelling of 20% cold worked 316 stainless steel fuel pin cladding and ducts |
1 |
E 1.99:conf-840612-17
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Recent field studies of dry deposition to surfaces in plant canopies |
1 |
E 1.99:conf-840614-1
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In-pile loss-of-flow TREAT test L05 with prototype fast reactor fuel |
1 |
E 1.99:conf-840614-2
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Heat-transfer calculations for a potted (solid matrix embedded) subassembly |
1 |
E 1.99: conf-840614-3
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Digraph matrix analysis applications to systems interactions |
1 |
E 1.99:conf-840614-4
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FRAS3 analysis of transient fission-gas behavior in PNL-10 fuel. [LMFBR] |
1 |
E 1.99:conf-840614-5
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Correlation for downward melt penetration into a miscible low-density substrate |
1 |
E 1.99:conf-840614-7
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Reactor shutdown system unavailability improvement by using a system of continuous data validation |
1 |
E 1.99:conf-840614-8
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Development of the three-dimensional SHAPS code capabilities for application to LMFBR piping systems |
1 |
E 1.99:conf-840614-10
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Helium/solid powder O-ring leakage correlation experiments using a radiotracer |
1 |
E 1.99: conf-840614-11
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Assessment of the response of spent fuel transports to malevolent acts |
1 |
E 1.99: conf-840614-13
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Status, plans, and capabilities of the Nuclear Criticality Information System |
1 |
E 1.99: conf-840614-14
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FIRST STEP blanket structure and fuel assembly design |
1 |
E 1.99: conf-840614-15
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FIRST STEP towards ICF commercialization |
1 |
E 1.99: conf-840614-16
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Nuclear electric capacity expansion in Mexico system effects of reactor size and cost. |
1 |
E 1.99:conf-840614-17
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RELAP/FRAP-T6 analysis of seized and sheared shaft accidents. [PWR] |
1 |