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Proceedings of the International Topical Meeting on Advanced Reactors Safety : Pittsburgh, Pennsylvania, April 17 - 21, 1994 / sponsored by the American Nuclear Society's Nuclear Reactor Safety Division and Pittsburgh Section ... In cooperation with the International Atomic Energy Agency ; Vol. 1
TIBKAT | 1994| -
Proceedings of the International Topical Meeting on Advanced Reactors Safety : Pittsburgh, Pennsylvania, April 17 - 21, 1994 / sponsored by the American Nuclear Society's Nuclear Reactor Safety Division and Pittsburgh Section ... In cooperation with the International Atomic Energy Agency ; Vol. 2
TIBKAT | 1994| -
Simulation of Hydrogen Transport with Mitigation Using the 3D Field Code GASFLOW
British Library Conference Proceedings | 1997| -
WGOTHIC Noding and Parametric Studies of a Passively-Cooled Small Rating PWR Containment
British Library Conference Proceedings | 1997| -
Containment Design of the European Pressurized Water Reactor (EPR)
British Library Conference Proceedings | 1997| -
Underground Reactor Containments: An Option for the Future?
British Library Conference Proceedings | 1997| -
LWR Severe Accident Research Accomplishments and Future Plans
British Library Conference Proceedings | 1997| -
Large-Scale Experiments on Ex-Vessel Core Melt Behaviour
British Library Conference Proceedings | 1997| -
Safety of a Light Water Cooled Reactor Operating at Supercritical Pressure
British Library Conference Proceedings | 1997| -
ROSA-AP600 Experiment Simulating a Steam Generator Tube Rupture Transient
British Library Conference Proceedings | 1997| -
A Design Study on a Gas Expansion Module to Enhance the Core Safety of the Demonstration Fast Breeder Reactor
British Library Conference Proceedings | 1997| -
Advanced Process Simulation with APROS for VVER-91, the Next Generation Reactor Design for VVER-1000
British Library Conference Proceedings | 1997| -
Advanced Man-Machine Interface Systems and Advanced Information Management Systems Programs
British Library Conference Proceedings | 1997| -
Effective Control Volume Based Method for Predicting Temperature Field and Heat Fluxes in Reactor Vessel
British Library Conference Proceedings | 1997| -
Numerical Analysis on the Turbulent Natural Convection in a Long Pipeline with Thermal Stratification
British Library Conference Proceedings | 1997| -
An Integrated Approach Between Primary System and Containment to Evaluate the Source Term in Advanced LWRs
British Library Conference Proceedings | 1997| -
A Design Reliability Assurance Program for Korean Next Generation Reactor
British Library Conference Proceedings | 1997|
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