Call Number (LC) Title Results
E 1.99:conf-800607--9 Measured performance of four PWR liquid radioactive waste treatment systems 1
E 1.99:conf-800607--11 Fission gas induced fuel swelling in low and medium burnup fuel during high temperature transients. [PWR] 1
E 1.99:conf-800607--12 Short collision time approximation for neutron scattering using discrete frequency distributions 1
E 1.99:conf-800607--13 FRAP-T5 predictions during reactor shutdown events. [PWR; BWR] 1
E 1.99:conf-800607--14 Fuel rod stored energy estimates for the LOFT LOCA tests 1
E 1.99:conf-800607--15 Assessment of molten debris freezing in a severe RIA in-pile test. [PWR; BWR] 1
E 1.99:conf-800607--16 Vapor explosion in the RIA-ST-4 experiment. [BWR] 1
E 1.99: conf-800607-18 Trace identification of cesium and sodium in neutral beam research 1
E 1.99:CONF-800607-19 Accounting for demand failures in Markovian analyses 1
E 1.99:conf-800607--20 Radioactive gas and hydrogen removal after a LOCE at the LOFT Facility 1
E 1.99: conf-800607-21 Overview of beneficial uses of nuclear fission products 1
E 1.99: conf-800607-22 Calculation of the CANON experiment using the TRAC code. [PWR; BWR] 1
E 1.99: conf-800607-23 OTSG modeling for the analysis of the TMI incident 1
E 1.99: conf-800607-24 Relating surveillance capsule measurements to pressure vessel damage 1
E 1.99:conf-800607--26 Evaluation of verification methods for input-accountability measurements 1
E 1.99:conf-800607--27 Department of Energy low-level waste management strategy 1
E 1.99:conf-800607--28 Irradiated Type 304 SS bend test ductility 1
E 1.99:conf-800607--29 Blanket design considerations for fast reactor oxide fuel systems based on CRBRP experience 1
E 1.99:conf-800607--33 Final design analyses of CRBRP fuel rod 1
E 1.99: conf-800607-34 Energy dependence of the ²³⁸U thermal capture cross section. [25 to 450°C] 1