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Kernkraftwerk
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Examining yankee plant performance in 1965
Testing the validity of the International Atomic Energy Agency (IAEA) safety culture model
The Safety Culture Enactment Questionnaire (SCEQ): Theoretical model and empirical validation
On the Use of Selected 4th Generation Nuclear Reactors in Marine Power Plants
Development of a computerized risk management system for international NPP EPC projects
Development of a computerized risk management system for international NPP EPC projects
Three Mile Island Nuclear Station, Unit 1. Summary of Aircraft Impact Design
Frg-0 II Experiment. Sixth Status Report, Condition 12/31/71
The role of nuclear power and nuclear propulsion in the peaceful exploration of space
P122C1 and P122C3 Analytical Performance Evaluation Summary
Frg-O-II Experiment. 4TH Status Report, Status December 31, 1970
Integrated probabilistic analysis of nuclear power plant building damage due to an aircraft crash
Radiative Energy Transport in a Plasma Reactor (Gas-Core Reactor)
Safety Report for Hot Laboratory of the Geesthacht Reactor
Application of Possibilistic C-Means for Fault Detection in Nuclear Power Plant Data
N. S. Savannah. Safety Analysis Summary, Defueling Pages Inadvertently Omitted
N. S. Savannah. Safety Analysis Summary- Defueling
N. S. Savannah. Failure of Alarm Systems
N. S. Savannah. Operations Report, November 9, 1970-March 31, 1971
N. S. Savannah. Technical Specifications, Changes to Section 7, Defueling
N. S. Savannah. Dropping of Fuel Element
N. S. Savannah. Modification of Pier Alarm Circuit
Transformable Elements of the Heat Removal System of Space Nuclear Power Plant
Design and Testing of Columbium-1 Zirconium Reactor Pressure Vessels
Quad-Cities Station, Units 1 and 2. Appendix a and Appendix B to Dpr-29 and Dpr-30, Proposed Change
Safety of German Designed Light Water-Reactors
Magnetic Moments and Vehicle Torques in the Snap 10A
Frg-0 II Experiment. Fifth Status Report, Condition 6/30/71
Probabilistic Assessment of Tornado-Borne Missile Speeds