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Corium (nuclear reactor)
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A Window Into the Meltdown Events at the Fukushima Daiichi Nuclear
Ex-Vessel Steam Explosion Analysis for Pressurized Water Reactor and Boiling Water Reactor
A Comparative Study of Flammability Limit Models for H2/CO Mixture on the Applicability of Severe Accident Conditions
The Results of Two Recent Corium-Water Thermal Interaction (CWTI)
NUREG/CR-6042, Rev. 2 [3:4] Appendix
09 Fr0200361
Analysis of Molten-Corium Concrete Interaction for Small Modular Reactor
Analytical Measurements of Fission Products During a Severe Nuclear Accident
Chapter 5 Development of the Core Melt Accident
Chernobyl 25 Years On
SEVERE ACCIDENT PHENOMENA Part 1: In-Vessel
DISCOMS: Distributed Sensing for Corium Monitoring and Safety P
Considerations Concerning the Strategy of Corium Retention in the Reactor Vessel
The Fukushima Daiichi Accident Technical Volume 5
Containment Loading During Severe Core Damage Accidents J
Progress on Ruthenium Release and Transport Under Air Ingress Conditions
Corium Lavas: Structure and Properties of Molten UO2-Zro2 Under Meltdown Conditions Received: 21 November 2017 O
Top View
Carbon Monoxide - Hydrogen Combustion Characteristics in Severe Accident Containment Conditions
Needs for Large Mass Prototypic Corium Experiments the PLINIUS-2 Platform C
Corium Experimental Thermodynamics: a Review and Some Perspectives
On March 12, 2012, the NRC Issued Order EA-12-050
Schedule | Symposium for the Basis of Nuclear Waste Management
In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor
Dose and Temperature Distribution in Spent Fuel Containing Material
Corium Retention Strategy on VVER Under Severe Accident Conditions
Topsafe2017-A0056
The Long-Term Effects of Nuclear Accidents
NKS-276, Consequences of Severe Radioactive Releases to Nordic
Modelling of Corium Stratification in the Lower Plenum of a Reactor Vessel
SAFEST Roadmap for Corium Experimental Research in Europe C
On-Line Measurements of Ruo 4 During a PWR Severe Accident S
Response to a Request for Additional Information Regarding ANP
Chernobyl Investigation: What Can Material Scientists Learn
A Linac-Based Neutron Source
Master Thesis Gamma Spectrometry Analysis Of
The Reality of the Fukushima Radioactive Water Crisis Shaun Burnie Greenpeace Germany
Density Stratification and Fission Product Partitioning in Molten Corium Phases
Results of First Experiments on COLIMA Facility Related to VVER-440 - Presentation of Planned VULCANO and KROTOS Tests
Fabricating Fukushima Daiichi In-Vessel and Ex-Vessel Fuel Debris Simulants for the Development and Qualification of Laser Cutting Technique Christophe Journeau, J
Division Name Will
5.5. Release of Fission Products During a Core Melt Accident
Analysis METHODOLOGY for RBMK-1500 CORE Safety AND
L'essai PLINIUS/COLIMA CA-U3 Sur Le Relâchement Des Aérosols De
Long-Term Aging of Chernobyl Fuel Debris: Coriumand “Lava”
Step 4 Assessment of Severe Accidents for the UK Advanced Boiling Water Reactor
Neutron-Gamma Flux and Dose Calculations for Feasibility Study of DISCOMS Instrumentation in Case of Severe Accident in a GEN 3 Reactor
Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)
5.4. Retention and Cooling of Corium Inside and Outside the Reactor Vessel 5.4.1
Review of Literature on Ruthenium Behaviour in Nuclear Power Plant Severe Accidents Charles Madic, Christian Mun, Laurent Cantrel
The ABWR Plant General Description
Behavior of a Corium Jet in High Pressure Melt Ejection from a Reactor Pressure Vessel