Keywords: سیستم خنک کننده هسته اورژانس; ECCS; emergency core cooling system; ICET; integrated chemical effects tests; ICP-AES; inductively coupled plasma atomic emission spectroscopy; LOCA; loss of coolant accident; NaTB; sodium tetraborate; NMR; nuclear magnetic resonance; PHWR; pressurized he
مقالات ISI سیستم خنک کننده هسته اورژانس (ترجمه نشده)
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Keywords: سیستم خنک کننده هسته اورژانس; ASDV; atmospheric steam discharge valves; CT; calandria tube; CV; calandria vessel; ECCS; emergency core cooling system; EOP; emergency operating procedure; IH; inlet header; MSSV; main steam-line safety valve; OH; outlet header; OPRD; over pressure ruptu
Discussion on emergency response capability configuration for inherent safe HTR
Keywords: سیستم خنک کننده هسته اورژانس; DBAs; Design Basis Accidents; ICPD; Ingestion and Commodities planning distance; EPZ; Emergency Planning Zone; FCPZ; Food control planning zone; IEPZ; Ingestion Emergency Planning Zone; ECCS; Emergency Core Cooling System; OILs; Operational Intervention L
Effect of eccentricity of pressure tube on circumferential temperature distribution of PHWR fuel bundle under postulated accident condition
Keywords: سیستم خنک کننده هسته اورژانس; PT; Pressure Tube; CT; Calandria Tube; LOCA; Loss of Coolant Accident; ECCS; Emergency Core Cooling System; IPHWR; Indian Pressurized Heavy Water Reactor; LOCA; ECCS; Fuel bundle; PT; CT; Moderator;
Numerical investigation of in-vessel core coolability of PWR through an effective safety injection flow model using MELCOR simulation
Keywords: سیستم خنک کننده هسته اورژانس; SAMG; In-vessel coolability; Safety injection flow map; Oxidation heat; Core exit temperature; MELCOR; ADV; Atmospheric Dump Valve; AFW; Auxiliary Feed Water; BWR; Boiling Water Reactor; CDV; Condenser Dump Valve; CET; Core Exit Temperature; CV; Control V
Boundary identification between LBLOCA and SBLOCA based on stratification and temperature gradient in two-phase PTS
Keywords: سیستم خنک کننده هسته اورژانس; BNPP; Bushehr Nuclear Power Plant; CFD; Computational Fluid Dynamics; DCC; Direct Contact Condensation; ECCS; Emergency Core Cooling System; FSAR; Final Safety Analysis Report; HPIS; High Pressure Injection System; LBLOCA; Large Break Loss OF Coolant Acci
Severe accident management measures for a generic German PWR. Part II: Small-break loss-of-coolant accident
Keywords: سیستم خنک کننده هسته اورژانس; Severe accident analysis; SBLOCA; PWR; Accident management measures; ACCU; Accumulator; AMM; Accident management measure; ATHLET(-CD); Analyse der Thermohydraulik von Lecks und Transienten/Analysis of thermal-hydraulics of leak and transients (with core d
Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2.0
Keywords: سیستم خنک کننده هسته اورژانس; ACCUs; Accumulators; AM; Accident Management; CET; Core Exit Temperature; CVCS; Chemical and Control Volume System; DGs; Diesel Generators; ECCS; Emergency Core Cooling System; EOPs; Emergency Operating Procedures; FOM; Figure of Merit; FW; Feedwater; HPI
Full length channel Pressure Tube sagging under completely voided full length pressure tube of an Indian PHWR
Keywords: سیستم خنک کننده هسته اورژانس; PT; Pressure Tube; CT; Calandria Tube; LOCA; Loss of Coolant Accident; ECCS; Emergency Core Cooling System; CANDU; CANada Deuterium Uranium; PHT; primary heat transport; PHWR; Pressurized Heavy Water Reactor; LOCA; Sagging; Pressure Tube; Calandria Tube;
Investigation of SAM measures during selected MBLOCA sequences along with Station Blackout in a generic Konvoi PWR using ASTECV2.0
Keywords: سیستم خنک کننده هسته اورژانس; ACCUs; accumulators; AM; Accident Management; CET; Core Exit Temperature; ECCS; Emergency Core Cooling System; FOM; Figure of Merit; HPIS; High Pressure Injection System; LP; lower plenum; LPIS; Low Pressure Injection System; MBLOCA; Medium Break LOCA; MC
Analysis of primary bleed and feed strategies for selected SBLOCA sequences in a German Konvoi PWR using ASTEC V2.0
Keywords: سیستم خنک کننده هسته اورژانس; ACCUs; accumulators; AM; accident management; CET; core exit temperature; DGs; diesel generators; ECCS; emergency core cooling system; EFWS; emergency feed water system; FOM; figure of merit; HPIS; high pressure injection system; LP; lower plenum; LPIS; l
The accumulator effects on in-vessel severe accident progression of a three loop PWR nuclear power plant in a SBLOCA without safety injection system
Keywords: سیستم خنک کننده هسته اورژانس; Severe accident; Accumulator; Emergency core cooling system; LOCA; Lower head; In-vessel;
Evaluation of JRC source term methodology using MAAP5 as a fast-running crisis tool for a BWR4 Mark I reactor
Keywords: سیستم خنک کننده هسته اورژانس; A; activity; AC; alternating current; ASTEC; accident source term evaluation code; BWR; boiling water reactor is a type of light water nuclear reactor; DC; direct current; DOSE; MAAP5 module for the dose calculation; ECCS; emergency core cooling system; E
Development, validation and application of multi-point kinetics model in RELAP5 for analysis of asymmetric nuclear transients
Keywords: سیستم خنک کننده هسته اورژانس; D. Reactor engineering; ASDV; atmospheric steam dump valve; ECCS; emergency core cooling system; IRV; instrumented relief valve; IQS; improved quasi-static; LOCA; loss of coolant accident; LORA; loss of regulation accident; LWR; light water reactor; NPP;
HAZOP application for the nuclear power plants decommissioning projects
Keywords: سیستم خنک کننده هسته اورژانس; ALARA; As Low As Reasonably Achievable; AWT; annular water tank; D & D; dismantling and decontamination; ECCS; Emergency Core Cooling System; EU; European Union; FEU; fume extract unit; HAZOP; hazards and operability assessment procedure; HEPA; high effic
Application of 3-D coupled code QUABOX/CUBBOX-ATHLET for RBMK-1000 vapor reactivity coefficient measurements
Keywords: سیستم خنک کننده هسته اورژانس; AA; additional absorber; CV; check valve; CPS; control and protection system; CR; control rod; DS; drum-separator; ECCS; emergency core cooling system; FA; fuel assembly; FC; fuel channel; FWP; feed water pump; GDH; group distribution header; GRS; Gesells
Steam Line Break investigation at full power reactor for VVER-1000/V320
Keywords: سیستم خنک کننده هسته اورژانس; AFWS; auxiliary feed water system; BRU-A; steam dump to atmosphere (SDTAF); BRU-K; steam dump to condenser; CSF; critical safety function; CV; check valve; ECCS; emergency core cooling system; EFW; emergency feed water; EFWS; emergency feed water system;
Negative pressure difference evaluation of Lungmen ABWR containment by using GOTHIC
Keywords: سیستم خنک کننده هسته اورژانس; 1D; one-dimensional; ABWR; Advanced Boiling Water Reactor; BOP; Balance of Plant; BWR; Boiling Water Reactor; CST; condensate storage tank; ECCS; Emergency Core Cooling System; FSAR; Final Safety Analysis Report; FWLB; feedwater line break; HPCF; High Pre
Small and Medium sized Reactors (SMR): A review of technology
Keywords: سیستم خنک کننده هسته اورژانس; 4S; Super-Safe, Small and Simple; AECL; Atomic Energy of Canada Limited; AHWR; Advanced Heavy Water Reactor; ALMCR; Advanced Liquid Metal Cooled Reactor; BWR; Boiling Water Reactor; CANDU; CANadian Deuterium Uranium; CAREM; Central Argentina de Elementos
Investigation of station blackout scenario in VVER440/v230 with RELAP5 computer code
Keywords: سیستم خنک کننده هسته اورژانس; AFW; auxiliary feed water; AFWP; auxiliary feed water pump; ALSS; automatic loading sequence system; BAS; Bulgarian Academy of Sciences; BRU-A; steam dumping device on the main steam header; BRU-K; steam dumping device to the condenser; BZOK; fast acting
Long-term pressure and temperature analysis and suppression pool mixing of Lungmen ABWR containment
Keywords: سیستم خنک کننده هسته اورژانس; 1D; one-dimensional; 2D; two-dimensional; 3D; three-dimensional; ABWR; Advanced Boiling Water Reactor; BOP; Balance of Plant; BWR; Boiling Water Reactor; DID; Defense In Depth; ECCS; Emergency Core Cooling System; FSAR; Final Safety Analysis Report; FWLB;
A study of the effectiveness of defense echelon design of ABWR/LMNPP plant for mitigating LOCA accident
Keywords: سیستم خنک کننده هسته اورژانس; Emergency core cooling system; High pressure core flooding system; Defense echelon;
An innovative pool with a passive heat removal system
Keywords: سیستم خنک کننده هسته اورژانس; Heat exchanger; Nuclear; Passive systems; Residual heat removal system; Emergency Core Cooling System