Call Number (LC) Title Results
E 1.99:nureg/cr-0631 Quantitative assessment of aquatic impacts of power plants 1
E 1.99:nureg/cr-0649 Spent fuel heatup following loss of water during storage. [PWR; BWR] 1
E 1.99:nureg/cr-0658 Mathematical simulation of sediment and contaminant transport in surface waters. Annual report, October 1977 - September 1978 1
E 1.99:nureg/cr-0672-add.2 Technology, safety and costs of decommissioning a reference boiling water reactor power station. Classification of decommissioning wastes. Addendum 2 1
E 1.99:nureg/cr-0672-add.3 Technology, safety and costs of decommissioning a reference boiling water reactor power station Technical support for decommissioning matters related to preparation of the final decommissioning rule. 1
E 1.99:nureg/cr-0672-add.4 Technology, safety and costs of decommissioning a reference boiling water reactor power station Comparison of two decommissioning cost estimates developed for the same commercial nuclear reactor power station. 1
E 1.99:nureg/cr-0672-v-1 Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979 1
E 1.99:nureg/cr-0672-v-2 Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979 1
E 1.99:nureg/cr-0672-vol.1 Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1 1
E 1.99:nureg/cr-0672-vol.2 Technology, safety and costs of decommissioning a reference boiling water reactor power station. Appendices. Volume 2 1
E 1.99:nureg/cr-0674 Benchmark critical experiments on low-enriched uranium oxide systems with H/U = 0. 77 1
E 1.99:nureg/cr-0678 Analysis of the heat and mass transfer processes of a UO/sub 2/ bubble in sodium for the Fuel Aerosol Simulant Test (FAST). [LMFBR]
Analysis of the heat and mass transfer processes of a UO₂ bubble in sodium for the Fuel Aerosol Simulant Test (FAST). [LMFBR] 		2
E 1.99:nureg/cr-696 Cladding embrittlement during postulated loss-of-coolant accidents. 1
E 1.99:nureg/cr-0718 Steam generator tube integrity program. Phase I report. [PWR] 1
E 1.99:nureg/cr-0722 Fission product release from highly irradiated LWR fuel 1
E 1.99:nureg/cr-0743 Transportation of radionuclides in urban environs draft environmental assessment. 1
E 1.99:nureg/cr-0763 Application of implicit numerical methods to problems in two-phase flow. [BWR; PWR] 1
E 1.99: nureg/cr-0773 Training and Qualifying Personnel for Performing Measurements for the Control and Accounting of Special Nuclear Material 1
E 1.99:nureg/cr-0774 Early mortality estimates for different nuclear accidents. Final Phase I report, October 1977-April 1979 1
E 1.99:nureg/cr-0797 Post-irradiation data analysis for NRC/PNL Halden assembly IFA-431 1