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Volumn 241, Issue 4, 2011, Pages 1152-1164

Analysis of different containment models for IRIS small break LOCA, using GOTHIC and RELAP5 codes

Author keywords

AB; ADS; Advanced pressurized reactor 1000 MWe; Advanced pressurized reactor 600 MWe; AP1000; AP600; Automatic depressurization system; Auxiliary building; Boiling water reactor; BWR; Chemical volume and control system; CVCS; DD; Direct vessel injection; Droplets diameter; Dry well; DVI; DW; EBT; EHRS; Electric power research institute; Emergency boration tank; Emergency heat removal system; EPRI; Generation of thermal hydraulic information for containments; GOTHIC; Heat transfer coefficient; HTC; International reactor innovative and secure; International standard problem number 42; IRIS; ISP 42; Large break LOCA; LBLOCA; LGMS; Light water reactor; LOCA; Long term gravity make up system; Loss of coolant accident; LWR; NEA; NPP; NRC; Nuclear energy agency; Nuclear power plant; Nuclear regulatory commission; OECD; Organization for economic co operation and development; PANDA; Passive containment cooling system; PAssive Nachw rmeabfuhr und DruckAbbau testanlange (passive decay heat removal and depressurization test facility); PCCS; Phenomena identification and ranking table; PIRT; Pressure suppression system; PSS; QT; Quench tank; RC; Reactor cavity; Reactor excursion and leak analysis program; Reactor vessel; Refuelling water storage tank; RELAP; RV; RWST; Safety analysis report; SAR; SBLOCA; SBWR; SIET; Simplified boiling water reactor; Simulatore Per Esperienze di Sicurezza (simulator for safety tests); Small break LOCA; Societ Informazioni Esperienze Termoidrauliche (company for information on thermal hydraulic experimentation); SPES; T H; Thermal hydraulic

Indexed keywords

AB; ADS; ADVANCED PRESSURIZED REACTOR - 600 MWE; AP1000; AP600; AUTOMATIC DEPRESSURIZATION SYSTEMS; AUXILIARY BUILDING; BWR; CVCS; DD; DIRECT VESSEL INJECTION; DROPLETS DIAMETER; DRY-WELL; DVI; DW; EBT; EHRS; ELECTRIC POWER RESEARCH INSTITUTE; EMERGENCY BORATION TANK; EMERGENCY HEAT REMOVAL SYSTEM; EPRI; GENERATION OF THERMAL-HYDRAULIC INFORMATION FOR CONTAINMENTS; GOTHIC; HTC; INTERNATIONAL REACTOR INNOVATIVE AND SECURE; INTERNATIONAL STANDARD PROBLEM NUMBER 42; IRIS; ISP-42; LARGE BREAK LOCA; LBLOCA; LGMS; LOCA; LONG-TERM GRAVITY MAKE-UP SYSTEM; LWR; NEA; NPP; NRC; NUCLEAR ENERGY AGENCY; NUCLEAR POWER; NUCLEAR REGULATORY COMMISSION; OECD; ORGANIZATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT; PANDA; PASSIVE CONTAINMENT COOLING SYSTEM; PCCS; PHENOMENA IDENTIFICATION AND RANKING TABLE; PIRT; PRESSURIZED REACTORS; PSS; QT; QUENCH TANKS; RC; REACTOR CAVITY; REACTOR EXCURSION AND LEAK ANALYSIS PROGRAM; REACTOR VESSEL; REFUELLING WATER STORAGE TANK; RELAP; RV; RWST; SAFETY ANALYSIS REPORT; SAR; SBLOCA; SBWR; SIET; SIMPLIFIED BOILING WATER REACTOR; SIMULATORE PER ESPERIENZE DI SICUREZZA (SIMULATOR FOR SAFETY TESTS); SMALL BREAK; SOCIET INFORMAZIONI ESPERIENZE TERMOIDRAULICHE (COMPANY FOR INFORMATION ON THERMAL-HYDRAULIC EXPERIMENTATION); SPES; T/H; THERMAL/HYDRAULIC;

EID: 79953246632     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2010.06.016     Document Type: Article
Times cited : (56)

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