Call Number (LC) Title Results
E 1.99:conf-9010185-4 Heavy-Section Steel Technology program overview 1
E 1.99: conf-9010185--5 Mechanical properties of cables exposed to simultaneous thermal and radiation aging 1
E 1.99: conf-9010185--7 Results of the DF-4 BWR (boiling water reactor) control blade-channel box test 1
E 1.99: conf-9010185--8 Accident sequence analysis for a BWR (Boiling Water Reactor) during low power and shutdown operations 1
E 1.99:conf-9010185-9 Improved eddy-current inspection for steam generator tubing 1
E 1.99: conf-9010185--10 Degradation modeling with application to aging and maintenance effectiveness evaluations 1
E 1.99:conf-9010185-11 Recent improvements in check valve monitoring methods 1
E 1.99: conf-9010185--12 A personal computer code for seismic evaluations of nuclear power plant facilities 1
E 1.99: conf-9010185--14 Evaluation of the leakage behavior of pressure-unseating equipment hatches and drywell heads 1
E 1.99: conf-9010185--15 Application of NUREG-1150 methods and results to accident management 1
E 1.99: conf-9010185--16 Advanced human-system interface design review guidelines 1
E 1.99: conf-9010185--17 MELCOR analysis of the TMI-2 accident 1
E 1.99: conf-9010185--18 MELCOR simulation of long-term station blackout at Peach Bottom 1
E 1.99:conf-9010185-19 Irradiation-induced sensitization of austenitic stainless steel in-core components 1
E 1.99:conf-9010185-20 Studies of aged cast stainless steel from the Shippingport reactor 1
E 1.99:conf-9010185-21 Estimation of fracture toughness of cast stainless steels in LWR (light water reactor) systems 1
E 1.99: conf-9010185--22 Diablo Canyon internal events PRA (Probabilistic Risk Assessment) review Methodology and findings. 1
E 1.99: conf-9010185--23 Status of the Surry low power and shutdown PRA (probabilistic risk analysis) 1
E 1.99: conf-9010185--25 Dependent failure analysis of NPP data bases 1
E 1.99: conf-9010185--26 Seismic testing and evaluation of relays past and future 1