Call Number (LC) Title Results
E 1.99:conf-831047-42 Simulation experiments on the radial pool growth in gas-releasing melting system. [PWR; BWR] 1
E 1.99:conf-831047-43 High-ramp-rate transient performance of EBR-II metallic driver fuel 1
E 1.99: conf-831047-44 Peach Bottom turbine-trip Test 3 analysis with RELAP5 code 1
E 1.99: conf-831047-45 Use of one delayed-neutron precursor group in transient analysis. [PWR; BWR] 1
E 1.99: conf-831047-46 Geochemistry of trench leachates from Maxey Flats disposal site 1
E 1.99: conf-831047-47 Risk evaluation of the containment overpressure relief system in a BWR-4, Mark-II nuclear power plant 1
E 1.99:conf-831047-48 Confirmation of the calculated breeding ratio for CRBRP 1
E 1.99:conf-831047-49 Benefit-cost-risk analysis of alternatives for greater-confinement disposal of radioactive waste 1
E 1.99:conf-831047-50 Fissile sample worths in the Uranium/Iron Benchmark 1
E 1.99:conf-831047-51 Spatial homogenization for plate-type critical assemblies. [LMFBR] 1
E 1.99: conf-831047-52 Pressure-vessel fluence reduction through selective fuel-assembly replacement 1
E 1.99: conf-831047-53 Comparative analysis of the CRDA using BNL-TWIGL and RAMONA-3B. [BWR] 1
E 1.99: conf-831047-54 Intra-assembly flow redistribution in LMFBRs a simple computational approach. 1
E 1.99:conf-831047-55 Neutron measurements and radiation damage calculations for fusion materials studies 1
E 1.99:conf-831047-56 Availability and uses of heavy-actinide isotopes 1
E 1.99:conf-831047-57 Experimental studies of a large heterogeneous LMFBR benchmark core, ZPPR-13A 1
E 1.99:conf-831047-58 Effects of reactor internals on primary containment response of an LMFBR during an HCDA 1
E 1.99:conf-831047-59 Magnitude of bias in Monte Carlo eigenvalue calculations 1
E 1.99:conf-831047-60 Droplet generation during core reflood. [PWR] 1
E 1.99:conf-831047-61 Alternate differencing technique for the synthetic method 1