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Void coefficient
Core Safety of Indian Nuclear Power Plants (Npps) Under Extreme Conditions
Liquid Metal Cooled Reactors: Experience in Design and Operation
INIS-Mf —14954 CA9600857
Core Design and Optimization of the High Conversion Small Modular Reactor
Description of the Advanced Gas Cooled Type of Reactor (AGR)
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Implications of the Accident at Chernobyl for Safety Regulation of Commercial Nuclear Power Plants in the United States Final Report
Monte Calrlo Modelling of Void Coefficient of Reactivity Experiment
Heavy Water Reactors: Status and Projected Development Designed in the Russian Federation
Fundamentals of Boiling Water Reactor (Bwr)
Advanced Fuels for Thermal Spectrum Reactors
US Reactor Safety Overview
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Reactivity Coefficients in Nuclear Reactors
The Chernobyl-4 Reactor and the Possible Causes of the Accident
XA9744488 IAEA-SM-346/2P the ENRICHMENT in Phwrs AS a TOOL to REDUCE the VOID COEFFICIENT Carla Notari Atomic Energy Commission
Safety of RBMK Reactors: Setting the Technical Framework
Small Reactors with Simplified Design
Top View
“Advanced” Isn't Always Better
Isothermal Temperature Reactivity Coefficient Measurement in Triga Reactor
Void Coefficient
Basics on Nuclear Power VVER 440 Loviisa, Finland
Pre-Conceptual Study of Small Modular Pbbi-Cooled Nitride Fuel Reactor Core Characteristics
The Chernobyl Reactor: Design Features and Reasons for Accident
RBMK Reactors | Reactor Bolshoy Moshchnosty Kanalny | Positive Void Coefcient 1/24/15, 3:10 PM
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ACTIVITIES in ARGENTINA RELATED to the USE of SLIGHTLY ENRICHED URANIUM in HEAVY WATER REACTOR Npps
The Dual Fluid Reactor
Sodium-Cooled Fast Reactors,” Proceedings of the International Conference on the Safety of Fast Reactors, Aix-En-Provence, September 19–22, 1967, Pp
The German Fast Breeder Program
MIT | the Future of Nuclear Energy in a Carbon-Constrained World
Improving the Performance of the SLIMR Design Introducing a 3-Pass Core Design and Neutronic-Thermalhydraulic Coupling Dennis Krijger
814 Transactions of the American Nuclear Society, Vol. 114, New
Analysis of the Reactivity Coefficients and the Stability of a Bwr Loaded with Mox Fuel
Fast Spectrum Molten Salt Reactor Options
Chernobyl – 30 Years on Fiona Macleod