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