Call Number (LC) Title Results
E 1.99: conf-930103--summ Summary of space nuclear reactor power systems, 1983--1992 1
E 1.99:conf-930105--1 Photobiotechnology Application of photosynthesis to the production of renewable fuels and chemicals. 1
E 1.99: conf-930107--1 Apical Cu-O bond in YBa[sub 2]Cu[sub 3]O[sub 7-[delta]] superconductors by XAFS
Apical Cu-O bond in YBa₂Cu₃O{sub 7-{delta}} superconductors by XAFS 		2
E 1.99: conf-930108--5 An interface configuration experiment on USML-1 2
E 1.99: conf-930111--1 The heating and cooling of WZ Sge 2
E 1.99: conf-930116--1 Core melt progression and consequence analysis methodology development in support of the Savannah River Reactor PSA 1
E 1.99: conf-930116--2 Risk-based configuration control Application of PRA in improving technical specifications and operational safety. 2
E 1.99: conf-930116--3 Requirements and capabilities of PSA for safety management applications 1
E 1.99: conf-930116--4 A risk-based evaluation of action requirements for failures in systems required for shutdown 2
E 1.99:conf-930116-8 The Centralized Reliability Data Organization (CREDO) Past, present, and future. 1
E 1.99: conf-930116--9 PSA uncertainties introduced by use of the PARTITION computer code for source term clustering. [Probability Safety Assessment (PSA)] 1
E 1.99: conf-930116--11 Risk-based configuration control Application of PSA in improving technical specifications and operational safety. 2
E 1.99: conf-930116--13 Probabilistic risk assessment for the Los Alamos Meson Physics Facility worst-case design-basis accident 2
E 1.99: conf-930116--14 Limited-scope probabilistic safety analysis for the Los Alamos Meson Physics Facility (LAMPF) 2
E 1.99: conf-930116--19 Risk management activities at the DOE Class A reactor facilities 2
E 1.99: conf-930116--20 The EBR-II Probabilistic Risk Assessment Results and insights. 2
E 1.99: conf-930116--22 A PRA case study of extended long term decay heat removal for shutdown risk assessment 2
E 1.99: conf-930116--23 Review process and quality assurance in the EBR-II probabilistic risk assessment 2
E 1.99: conf-930116--24 Fault tree analysis of the EBR-II reactor shutdown system 2
E 1.99: conf-930116--25 Probabilistic treatment of rod run-in accident initiators and the reactivity feedback responses in EBR-II 2