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- Bui, Ha [remove] 1
- 620.00452 1
- ADAPT Analysis of Dynamic Accident Progression Trees -- ADS Accident Dynamic Simulation -- BWR Boiling Water Reactor -- CAD Computer-Aided Design -- CASA Containment Accident Stochastic Analysis -- CCBE Common Cause Basic Event -- CCCMT Continuous Cell-To-Cell-Mapping Technique -- CCF Common Cause Failure -- CDF Core Damage Frequency -- CET Continuous Event Tree -- CFAST Consolidated Model of Fire Growth and Smoke Transport -- CFD Computational Fluid Dynamics -- CFR Code of Federal Regulations -- CHLE Chemical Head Loss Experiments -- CSHL Clean Strainer Head Loss -- CSS Containment Spray System -- DDET Discrete Dynamic Event Tree -- DEGB Double Ended Guillotine Break -- DET Dynamic Event Tree -- DETAM Dynamic Event Tree Analysis Method -- DYLAM Dynamic Logical Analytical Methodology -- ECCS Emergency Core Cooling System -- EMRALD Event Modeling Risk Assessment using Linked Diagrams -- ERM Enterprise Risk Management -- ET Event Tree -- FDS Fire Dynamics Simulator -- FLEX Diverse and Flexible Coping Strategy -- FSM Failure Simulation Module -- FT Fault Tree -- GDC General Design Criteria -- GIM Global Importance Measure -- GL Generic Letter -- GSI-191 Generic Safety Issue 191 -- HHSI High Head Safety Injection -- HRR Heat Release Rate -- HRA Human Reliability Analysis -- IE Initiating Event -- IM Importance Measure -- I-PRA Integrated Probabilistic Risk Assessment -- KPM Key Performance Measure -- LERF Large Early Release Frequency -- LHS Latin Hypercube Sampling -- LHSI Low Head Safety Injection -- LN Logic Node -- LOCA Loss of Coolant Accident -- LWR Light Water Reactor -- MCDET Monte Carlo Dynamic Event Tree -- MCS Minimal Cut Set -- MELCOR Methods for Estimation of Leakages and Consequences of Releases -- NEI Nuclear Energy Institute -- NPP Nuclear Power Plant -- NPSH Net Positive Suction Head -- NRC U.S. Nuclear Regulatory Commission -- PPoF Probabilistic Physics-of-Failure -- PRA Probabilistic Risk Assessment -- PWR Pressurized Water Reactor -- RAVEN Reactor Analysis and Virtual Control Environment -- RELAP Reactor Excursion and Leak Analysis Program -- ROM Reduced Order Model -- RoverD Risk-informed Over Deterministic -- RWST Reactor Water Storage Tank -- SCAIS Simulation Code System for Integrated Safety Assessment -- SimPRA Simulation-based Probabilistic Risk Assessment -- S-IPM Simulation-Informed Probabilistic Methodology -- SoTeRiA Socio-Technical Risk Analysis -- SRM Staff Requirements Memorandum -- SSCs Structures, Systems, and Components -- TH Thermal Hydraulic -- TRACE TRAC/RELAP Advanced Computational Engine -- ZOI Zone of Influence 1
- Fiabilité -- Périodiques 1
- Industrial safety -- Periodicals 1
- Integrated Probabilistic Risk Assessment (I-PRA) -- Generic Safety Issue 191 (GSI-191) -- Nuclear promise -- Fire PRA -- Risk-informed regulation -- Dynamic PRA 1
- Reliability (Engineering) -- Periodicals 1
- System safety -- Periodicals 1
- Sécurité des systèmes -- Périodiques 1
- Sécurité du travail -- Périodiques 1