RETU: The Finnish Research Programme on Reactor Safety: Interim Report 1995 - May 1997

Keyphrases

• Accident Management 100%
• Reactor Safety 100%
• Nuclear Fuel 66%
• Risk Management 66%
• Safety-related 33%
• Nuclear Reactor 33%
• Nuclear Power Plant 33%
• Severe Accident 33%
• Effective Method 33%
• Thermal-hydraulics 33%
• Three-dimensional (3D) 33%
• Calculation Method 33%
• VVER-440 33%
• Reactor Analysis 33%
• Plant Design 33%
• Analysis Code 33%
• System Concept 33%
• Preventive Measures 33%
• Nuclear Power Plant Safety 33%
• National Research Program 33%
• Computer Code 33%
• New Fuel 33%
• Model Solution 33%
• Probabilistic Method 33%
• Reactor Core 33%
• Accident Analysis 33%
• Continual Learning 33%
• Program Research 33%
• Passive Safety 33%
• Management Risk 33%
• Power Transients 33%
• Reactivity Transients 33%
• Management Methods 33%
• Flow Model 33%
• Control Room Design 33%
• Safety Critical Organizations 33%
• Human Safety 33%
• Hydraulic Test 33%
• High Burnup 33%
• Parallel Channels 33%
• Human Reliability 33%
• Operating Margin 33%
• Safe Limit 33%
• Severe Accident Mitigation 33%
• Accident Behaviour 33%
• Dynamic Reactor 33%
• International Tests 33%
• Fuel Design 33%
• Numerical Solution Methods 33%
• Event Sequences 33%
• Reactivity Accident 33%
• Human Competencies 33%
• Channel Test 33%

INIS

• safety 100%
• research programs 100%
• reactor safety 100%
• accidents 75%
• design 75%
• accident management 75%
• risks 50%
• management 50%
• transients 50%
• validation 50%
• nuclear power plants 50%
• severe accidents 50%
• humans 50%
• nuclear fuels 50%
• tools 25%
• decision making 25%
• assessments 25%
• control 25%
• environment 25%
• nuclear reactors 25%
• calculation methods 25%
• fuels 25%
• operation 25%
• steady-state conditions 25%
• power 25%
• learning 25%
• computer codes 25%
• volume 25%
• range 25%
• evaluation 25%
• reactivity 25%
• probabilistic estimation 25%
• thermal hydraulics 25%
• maintenance 25%
• testing 25%
• reliability 25%
• burnup 25%
• mitigation 25%
• trains 25%
• wwer type reactors 25%
• reactor kinetics 25%
• numerical solution 25%
• personnel 25%
• margins 25%
• flow models 25%
• test facilities 25%
• reactor cores 25%
• control rooms 25%

Engineering

• Severe Accident 100%
• Nuclear Power Plant 100%
• Reactor Safety 100%
• Nuclear Fuel 100%
• Burnup 50%
• Thermal Hydraulics 50%
• System Safety 50%
• Experimental Work 50%
• Test Program 50%
• Reactor Core 50%
• Control Room 50%
• Loop Test 50%
• Analysis Code 50%
• Probabilistic Method 50%
• Parallel Channel 50%
• Fuel Design 50%
• Transients 50%
• Solution Method 50%
• Reactor Dynamics 50%
• Test Facility 50%
• Main Result 50%
• Nuclear Reactor 50%
• Flow Model 50%
• Numerical Solution 50%