Keywords: vvere; ADPV; Auto Depressurization Passive Valve; AHWR; Advanced Heavy Water Reactor; BARC; Bhabha Atomic Research Centre; DN; Diametre Nominel; I2S-LWR; Integral Inherently Safe Light Water Reactor; LOCA; Loss of Coolant Accident; PADS; Passive Auto Depressuriz
مقالات ISI vvere (ترجمه نشده)
مقالات زیر هنوز به فارسی ترجمه نشده اند.
در صورتی که به ترجمه آماده هر یک از مقالات زیر نیاز داشته باشید، می توانید سفارش دهید تا مترجمان با تجربه این مجموعه در اسرع وقت آن را برای شما ترجمه نمایند.
در صورتی که به ترجمه آماده هر یک از مقالات زیر نیاز داشته باشید، می توانید سفارش دهید تا مترجمان با تجربه این مجموعه در اسرع وقت آن را برای شما ترجمه نمایند.
Keywords: vvere; AEC; Atomic Energy Council; AOV; Air Operated Valve; ARIEL; Aerosol Removal & Iodine Elimination; BWR; Boiling Water Rector; CGN; China General Nuclear Power Corporation; CNNC; China National Nuclear Corporation; CNPE; China Nuclear Power Engineering Co.,
Keywords: vvere; Zirconium alloys; VVER; Transition; Instantaneous and cumulative corrosion rate; Cyclic nature of corrosion; Electrochemical impedance spectroscopy (EIS);
Keywords: vvere; Diffusion; ADF; Hexagonal; Reflector; VVER;
Keywords: vvere; BOC; beginning of cycle; DR; Dominance Ratio; EFPD; Equivalent Full Power Day; EOC; end of cycle; ES; Eigenvalue Separation; FIMA; Fissions per Initial Metal Atom; HTR; High Temperature Reactor; MCB; continuous energy Monte Carlo Burnup (code); MCNP; Mont
Keywords: vvere; BWR; boiling water reactor; EAC; environmentally assisted cracking; HE; hydrogen embrittlement; LWR; light water reactor; NPP; nuclear power plant; NRPV; nuclear reactor pressure vessel; PWR; pressurized water reactor; RPV; reactor pressure vessel; VVER;
Keywords: vvere; AERB; Atomic Energy Regulatory Board; BARC; Bhabha Atomic Research Centre; BARCOM; BARC Containment Model; BDBA; Beyond Design Basis Accident; CDP; Concrete Damage Plasticity; DBA; Design Basis Accident; DEC; Design Extension Condition; EAL; Emergency Air
Keywords: vvere; Natural circulation; PRHRS; RELAP5; VVER
Keywords: vvere; NPP; VVER; Personnel training; Mathematical modeling; Numerical experiments; Computer and full-scale simulators; Xenon oscillations; Nuclear reactor xenon stability
Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 2. Creep deformation and failure of the reactor
Keywords: vvere; Severe accident; Creep; VVER; Failure; Deformation; Inverse stratification; Simulation; Corium;
Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratificatio
Keywords: vvere; Severe accident; VVER; Inverse corium stratification; In-vessel melt retention; Critical heat flux; Reactor pressure vessel; Corium; Melt;
Experimental estimation of the effect of contact condensation of steam-gas mixture on VVER passive safety systems operation
Keywords: vvere; VVER; Steam generator; Condensation mode; Contact condensation; Non-condensable gases; Steam-gas mixture;
Experimental investigation of heat and mass exchange processes during operation of VVER steam generator in emergency condensing mode
Keywords: vvere; VVER; Steam generator; Passive safety systems; Passive heat removal system; Non-condensable gases; Steam-gas mixture;
Feasibility of using Gd2O3 particles in VVER-1000 fuel assembly for controlling excess reactivity
Keywords: vvere; Fuel assembly; VVER; Gd2O3 particle; reactivity; power distribution;
Determinants and considerations of Rosatom's external strategy
Keywords: vvere; Rosatom state nuclear energy corporation; Nuclear energy; External strategy; Nuclear power plant; Foreign operations; ÐO; Joint-stock company (ÐкâионеÑное обâ¯Ðµâ¿ÑÏо) - a type of public limited company in the Russian Federation; BN;
Safety analyses of reactor VVER 1000
Keywords: vvere; VVER; safety analysis; coupling;
In-service change in the flexural rigidity of the VVER-1000 fuel assemblies
Keywords: vvere; Fuel assembly; Fuel rod; VVER; Flexural rigidity; Fuel burnup; Spacer grid; FA skeleton; FA bowing;
Investigation of passive residual heat removal system for VVERs: Effects of finned type heat exchanger tubes
Keywords: vvere; Heat exchanger; Natural circulation; Passive residual heat removal system; VVER;
HAZOP application for the nuclear power plants decommissioning projects
Keywords: vvere; 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
Energy and exergy analyses of a VVER type nuclear power plant
Keywords: vvere; Nuclear power; VVER; Exergy; Energy; Reactor
Propagation noise calculations in VVER-type reactor core
Keywords: vvere; Propagation noise; Three dimensional; VVER; Forward approach; Adjoint approach;
Steam Line Break investigation at full power reactor for VVER-1000/V320
Keywords: vvere; 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;
Investigation of molten core-concrete interaction reactor benchmark test for VVER 1000
Keywords: vvere; Molten core-concrete interaction; VVER; Severe accident computer codes; Benchmark problem; ASTEC; Severe accident computer code; GEMINI2; Code for physico-chemistry calculation; MCCI; Molten core-concrete interaction; MEDICIS; Molten core-concrete i
A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments
Keywords: vvere; ACM; advanced cladding materials; AIC or Ag/In/Cd; silver-indium-cadmium; BWR; boiling water reactor; CEA; Commissariat à L'Energie Atomique; EC; European Commission; FP; fission product; GRS; Gesellschaft für Anlagen- und Reaktorsicherheit; IET;
Investigating the propagation noise in PWRs via closed-loop neutron-kinetic/thermal-hydraulic noise calculations
Keywords: vvere; Propagation noise; Neutron-kinetics; Thermal-hydraulics; Noise analysis; PWR; VVER;
Investigation of station blackout scenario in VVER440/v230 with RELAP5 computer code
Keywords: vvere; 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
VERONA V6.22 - An enhanced reactor analysis tool applied for continuous core parameter monitoring at Paks NPP
Keywords: vvere; 2D; two dimensional; 3D; three dimensional; AEKI; Atomic Energy Research Institute (Budapest, Hungary); BOC; beginning of cycle; CFD; computational fluid dynamics; CFX; widely used CFD code; C-PORCA; nodal diffusion code (used for core calculations at Pak
A cycle-specific cross-section update for real-time simulation of VVER-1000 core
Keywords: vvere; VVER; Real-time simulation; Core model; Cross sectionsADF, Assembly Discontinuity Factor; ADV, Atmospheric Dump Valve; BOP, Balance of Plant; EFPD, Effective Full-Power Days; ESFAS, Engineered Safety Feature Automation Systems; FA, Fuel Assembly; ICMS, In
Investigation of dry out of SFP for VVER440/V230 at Kozloduy NPP
Keywords: vvere; ANS; American national standard; BAS; Bulgarian academy of sciences; BRU-A; Steam dump valves to atmosphere (Bulgarian abbreviation); BRU-K; Steam dump valve to the condenser (Bulgarian abbreviation); EFWS; emergency feed water system; FSIV; fast safety i
Grounds of VVER-1000 fuel cladding life control
Keywords: vvere; Creep; Fuel; Cladding; Life; Control; VVER;
Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests
Keywords: vvere; AgInCd; silver-indium-cadmium; BR3; Belgian Reactor 3; BWR; boiling water reactor; B4C; boron carbide; FP; fission product; ISP; International Standard Problem; ISTP; International Source Term Programme; KIT; Karlsruhe Institute of Technology; LWR; li
Enhancement of COBRA-EN capability for VVER reactors calculations
Keywords: vvere; COBRA-EN; Thermal–hydraulic analysis; Automatic hexagonal; Subchannel; VVER; Power distribution
Thermal decomposition of hydrazine in sub- and supercritical water at 25Â MPa
Keywords: vvere; AVT; all volatile water treatment; GEN IV; generation IV nuclear energy systems; GERG; Groupe Européen de Recherche Gazières; HWC; hydrogen water chemistry; OT; oxygenated water treatment; ppb; part-per-billion, â¼1 μg/L at SATP; ppm; part-per-millio
Investigation of burnable poisons effects in reactor core design
Keywords: vvere; BAR; Chemical shim; VVER; Core design; Burnable poison; Reactivity coefficient
Sampling based uncertainty analysis of station blackout in PSB VVER integral test facility
Keywords: vvere; Accident analysis; Latin Hypercube Sampling (LHS); Station blackout (SBO); Sensitivity; Uncertainty; VVER;
Investigation of primary to secondary leakage at low power during “Hydro-test” for VVER440/V230 at Kozloduy NPP
Keywords: vvere; ANS; American national standard; BAS; Bulgarian Academy of Sciences; BRU-K; Steam Dumping Device to the Condenser (Bulgarian abbreviation); CSF; Critical Safety Function; EFWS; Emergency Feed Water System; FSIV; fast safety isolation valve; FWST; feed wat
Loss of ‘Core cooling’ at low power and cold condition of VVER-1000/V320
Keywords: vvere; Thermal–hydraulics; RELAP5/MOD3.2; Nuclear power plant safety; VVER; Low power and cold condition; Critical safety functionBRU-A, steam dump to atmosphere; BRU-K, steam dump to condenser; COP, cold overpressure protection; CSF, critical safety function; E
Systematic approach for the analytical validation of Kozloduy NPP, VVER-1000/V320 symptom based emergency operating procedures
Keywords: vvere; Thermal-hydraulics; Emergency operating procedures; RELAP5/MOD3.2; Nuclear power plant safety; VVER
Sensitivity calculations of PRZ water level during the Natural Circulation test at Unit 6 of Kozloduy NPP
Keywords: vvere; Thermal-hydraulics; RELAP5/MOD3.2; Code validation; Nuclear Power Plant safety; VVER; Natural Circulation
RELAP5/MOD3.2 blackout investigation for validation of EOPs for KNPP VVER-1000/V320
Keywords: vvere; Thermal–hydraulics; RELAP5/MOD3.2; Nuclear power plant safety; VVER; Natural circulation; Horizontal steam generator
NRI Řež solution of Exercise 3 of VVER-1000 Coolant Transient Benchmark – Phase 1 with coupled codes DYN3D–ATHLET
Keywords: vvere; VVER; Coolant Transient Benchmark; DYN3D–ATHLET coupled codes; 3-D simulation
Simulation of the VVER-1000 pump start-up experiment in the OECD/DOE/CEA V1000CT benchmark by the FLICA4/CRONOS2 coupled code system
Keywords: vvere; VVER; Benchmark; Pump start-up; Code coupling; Neutronic; Thermal–hydraulic
Impact of cross-section generation procedures on the simulation of the VVER-1000 pump startup experiment in the OECD/DOE/CEA V1000CT benchmark by coupled 3D thermal-hydraulics/neutron kinetics models
Keywords: vvere; V1000CT; Benchmark; VVER; Coupled; Cross section; HELIOS
OECD/DOE/CEA VVER-1000 coolant transient (V1000CT) benchmark – A consistent approach for assessing coupled codes for RIA analysis
Keywords: vvere; V1000CT; Benchmark; VVER; Coupled
Assessment study of the coupled code RELAP5/PARCS against the Peach Bottom BWR turbine trip test
Keywords: vvere; BE; best estimate; BPV; by-pass valve; BWR; boiling water reactor; CRISSUES; critical issues in nuclear reactor technology: a state of the art report; CS; cross-section; 3D; three-dimensional; EC; European Commission; IAEA; International Atomic Energy Age