Emergency Core Cooling System pipe crack incident at Tihange unit 1 plant
Roussel, G.; Organisation for Economic Co-operation and Development; Nuclear Energy Agency
German National Library of Science and Technology (GetInfo) (German)
Emergency Core Cooling System Verifications of Qinshan Phase II NPP Project
Yu, H.-x.; Huang, D.-s.
Emergency Core Cooling System Recirculation Issue Solutions for Less-than-Large-Break LOCAs-Panel
American Nuclear Society
The emergency core cooling system of light water reactors relies on a ready supply of debris-free water from the containment sump
Assessment of Core Cooling Capability of Emergency Core Cooling System in LBLOCA Condition for TAPS#3&4
Kumar, N.; Yadav, S.K.; Khan, T.A.
Assessment of the Emergency Core Cooling System (ECCS) Performance for Advanced Plant Designs Using WCOBRA/TRAC
Frepoli, C.; Nissley, M.; Ohkawa, K.
ICEM2009-16247 Modelling of Radiation Fields and Estimation of Doses During Dismantling of RBMK-1500 Reactor Emergency Core Cooling System
Poskas, P.; Simonis, A.; American Society of Mechanical Engineers
Advanced Reactor Passive Emergency Core Cooling System Stratified Flow Experiments and Characterization of Condensation Induced Water Hammer
Kadakia, H. J.; Williams, B.; Phoenix, W.
Estimation of radiation doses during dismantling a pressured tank of RBMK-1500 reactor emergency core cooling system
Simonis, A.; Adliene, D.; Lietuvos Energetikos institutas (Kaunas, Lithuania)
Estimation of radiation dose in dismantling pipelines of RBMK reactor emergency core cooling system
Simonis, A.; Lietuvos Energetikos institutas (Kaunas, Lithuania)
Proposed Concept of a Passive Water-Cooled Reactor Without Emergency Core Cooling System
Chang, S. H.; Baek, W. P.; Lee, G. J.
ICONE12-49308 Direct Vessel Vertical Injection for Advanced Emergency Core Cooling System
Yoon, S. H.; Suh, K. Y.; Yu, Y. H.
Direct vessel vertical injection for advanced emergency core cooling system
Yoon, S. H.; Yu, Y. H.; Suh, K. Y.
Experimental Investigation of Passive Emergency Core Cooling System
Peng, Y.-k.; Zheng, H.
Advanced Reactor Passive Emergency Core Cooling System Stratified Flow Experiments Project No: DE-FG07-03ID14500
Kadakia, H.; Williams, B.; Schultz, R. R.
HMT-97-154 Upgraded RBMKS Emergency Core Cooling System
Novoselsky, O. Y.; Smolin, V. N.; Karasev, V. B.
Analysis of the RBMK-1500 Type Reactor Emergency Core Cooling System Behavior, Taking into Account the Specified Hydraulic Characteristics of Fast Acting Motor Valves
Kaliatka, A.; Ognerubov, V.; Adomavicius, A.
Modifications to the Emergency Core Cooling System to Increase Flow to the Reactor
Baker, W. H.; Department of Energy, Washington, DC
BWR (Boiling Water Reactor) Refill-Reflood Program Task 4.4 - CCFL (Counter-Current Flow Limiting)/Refill System Effects Tests (30 deg Sector) Evaluation of ECCS (Emergency Core Cooling System) Mixing Phenomena
Findlay, J. A.; Nuclear Regulatory Commission, Washington, DC. Office of Nuclear Regulatory Research
RELAP5 Analysis of Passive Emergency Core Cooling System Tests
Assessment of Safety Margins in Zircaloy Oxidation and Embrittlement Criteria for ECCS (Emergency Core Cooling System) Acceptance
Williford, R. E.; Nuclear Regulatory Commission, Washington, DC. Office of Nuclear Regulatory Research
Simulation of Cold Leg Manifold Break and Station Blackout Revised Sequences for Reduced ECCS (Emergency Core Cooling System) in the N Reactor
Bolander, M. A.; Chapman, J. C.; Fletcher, C. D.
Engineered safety feature, an emergency core cooling system at Pakistan research reactor-1
Bokhari, I. H.; Mahmood, T.
Thermohydraulic Safety Analysis of Design Base Accident (DBA) for the Emergency Core Cooling System (ECCS) in Nuclear Power Plant (NPP) Stendal-1A of Soviet Type WWER-1000 with System Code ATHLET/FLUT
Kirmse, R.; Macek, J.; American Nuclear Society; Thermal Hydraulics Division
Unlimited Cooling Capacity of the Passive-Type Emergency Core Cooling System of the MARS Reactor
Caira, M.; Gramiccia, L.; Naviglio, A.
The Ongoing Challenge - Closing Emergency Core Cooling System Strainer Issues for Good
Scott, M.L.; Snodderly, M.R.
Advantages of Applying Cool Pump Technology to a Proposed Alternate Emergency Core Cooling System for the N Reactor
Beaver, T. R.; Department of Energy, Washington, DC
Influence of the injection point of the high-pressure emergency core cooling system on the temperature rise of the injected water in the circulation piping
Rybin, R. A.; Sidorov, V. G.; Dukina, I. A.
Analysis of the dynamic behaviour of the low pressure emergency core cooling system tank at Paks NPP
Tamas, K.; International Atomic Energy Agency
ICONE17-75931 Assessment of Reliability of Emergency Core Cooling System (ECCS) of Bushehr Nuclear Power Plant
Sotoudeh, M.; Sepanloo, K.
The design and experimental validation of an emergency core cooling system for a pool type research reactor
Torres, W. M.; Filho, B. D. B.; Ting, D. K. S.
Advanced Heavy Water Reactor (AHWR) LOCA Analysis with Loss of Emergency Core Cooling System (ECCS) for 200% Inlet Header Break
Kumar, R.; Gaikwad, A.; Lele, H. G.
Diversified Emergency Core Cooling in CANDU with a Passive Moderator Heat Rejection System
Spinks, N. J.; American Nuclear Society; Thermal Hydraulics Division
A system for emergency core cooling through high performance steam injector (SYNTHESIS)
Valisi, M.; Mazzocchi, L.; Meseth, J.
A System for Emergency Core Cooling Through High Performance Steam Injector (SYNTHESIS)
Valisi, M.; Galbiati, L.; Mazzocchi, L.
Passive Core Emergency Cooling System Test Research
Zheng, H.; Zhong, Y.-m.; Ma, J.
REMI/HEAT COOL : a model for evaluation of core heat-up and emergency core spray cooling system performance for light-water-cooled nuclear power reactors
Munthe Andersen, Jens G.
Structural design of replacement emergency core cooling filtration system (6-1907)
International Association for Structural Mechanics in Reactor Technology
Softening of thermal shock during start-up of emergency cooling systems for the core of VVÉR-1000 reactors
Report to the American Physical Society by the study group on light-water reactor safety
Lewis, H. W.; Budnitz, R. J.; Castleman, A. W.
Assessing the influence of uncertain factors in analyzing emergency processes at nuclear power stations equipped with VVER-1000 reactors
Kuznetsov, V.; Vorob’ev, Yu.; Mansuri, M.
Website Policies and Important Links Comments
WorldWideScience.org is maintained by the
U.S. Department of Energy's
Office of Scientific and Technical Information as the Operating Agent
for the WorldWideScience Alliance.