Call Number (LC) Title Results
E 1.99: conf-830609-59 Fuel-pin cladding transient failure strain criterion. [LMFBR] 1
E 1.99:conf-830609-60 Application of ²⁵²Cf-source driven noise analysis measurements for subcriticality of HFIR fuel elements 1
E 1.99:conf-830609-61 SEP operating history of the Dresden Nuclear Power Station Unit 2 1
E 1.99:conf-830609-62 Survey of shielding data and methods for fuel reprocessing applications 1
E 1.99:conf-830609-63 Preliminary analysis of fission gas behavior and fuel response during an LMFBR operational transient 1
E 1.99:conf-830609-64 Human factors in remote control engineering development activities 1
E 1.99: conf-830609-65 Application of nuclear resonance scattering for in vivo measurements 1
E 1.99:conf-830609-66 Nuclear engineering laboratory self regulated power oscillation experiments at the Health Physics Research Reactor 1
E 1.99:conf-830609-67 Axial location of cladding failure during a slow transient overpower TREAT test. [LMFBR] 1
E 1.99:conf-830609-68 Formation and transport of fission product aerosols 1
E 1.99:conf-830609-69 Analysis of closed-pool boilup using the TRANSIT-HYDRO code. [LMFBR] 1
E 1.99:conf-830609-70 Evaluation of molten lead mixing in sodium coolant by diffusion for application to PAHR. [LMFBR] 1
E 1.99:conf-830609-71 Fission-product aerosol sampling system for LWR experiments in the TREAT reactor 1
E 1.99:conf-830609-72 Downward penetration of hot UO₂ into basalt concrete 1
E 1.99:conf-830609-73 Experimental Breeder Reactor-II dynamic modeling and code verification 1
E 1.99:conf-830609-74 Criticality safety training at the Hot Fuel Examination Facility 1
E 1.99:conf-830609-75 Determination of the design excess reactivity for the TREAT Upgrade reactor 1
E 1.99:conf-830610-2 Characterization of Pu-contaminated soils from Nuclear Site 201 at the Nevada Test Site 1
E 1.99:conf-830610-3 Improved method of ²⁴¹Am analysis for Nevada Test Site soils 1
E 1.99: conf-830610-6 Analysis of the NAEG model of transuranic radionuclide transport and dose 1