Call Number (LC) Title Results
E 1.99: egg--2594 An assessment of BWR (boiling water reactor) Mark III containment challenges, failure modes, and potential improvements in performance 1
E 1.99: egg--2597 Models for estimation of service life of concrete barriers in low-level radioactive waste disposal 1
E 1.99: egg--2603 Radiation degradation in EPICOR-2 ion exchange resins 1
E 1.99: egg--2604 Low-level radioactive waste disposal facility closure 1
E 1.99: egg--2605 Effect of pH on the release of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resins collected from operating nuclear power stations 1
E 1.99: egg--2606 Simplified containment event tree analysis for the Sequoyah Ice Condenser containment 1
E 1.99: egg--2607 Pressure-dependent fragilities for piping components Pilot study on Davis-Besse Nuclear Power Station. 1
E 1.99: egg--2608-vol.1 Assessment of ISLOCA risk Methodology and application to a Babcock and Wilcox nuclear power plant. Volume 1, Main report. 1
E 1.99: egg--2608-vol.2 Assessment of ISLOCA risk Methodology and application to a Babcock and Wilcox nuclear power plant. Volume 2, Appendices A--H. 1
E 1.99: egg--2609 Proceedings of the symposium on inservice testing of pumps and valves 1
E 1.99: egg--2610 Determination of the bias in LOFT fuel peak cladding temperature data from the blowdown phase of large-break LOCA experiments 1
E 1.99: egg--2618 Light water reactor lower head failure analysis 1
E 1.99: egg--2627 Models and Results Database (MAR-D), Version 4. 0 1
E 1.99: egg--2628-vol.2 System Analysis and Risk Assessment system (SARA) Version 4.0 1
E 1.99:egg-2629 Development of magnetic resonance technology for noninvasive boron quantification 1
E 1.99: egg--2640 Risk analysis of highly combustible gas storage, supply, and distribution systems in PWR plants 1
E 1.99: egg--2644 Implications for accident management of adding water to a degrading reactor core 1
E 1.99: egg--2649 Assessment of ISLOCA risk Methodology and application to a Westinghouse four-loop ice condenser plant. 1
E 1.99: egg--2650 Assessment of ISLOCA risk-methodology and application to a combustion engineering plant 1
E 1.99:egg--2656 Public acceptability of the use of gamma rays from spent nuclear fuel as a hazardous waste treatment process 1