Keywords: Depressurization of the containment; Water spray; Decay rate constant; ASTEC; Sauter mean diameter;
مقالات ISI (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: Containment; Condensation; Evaporation; Sump; TOSQAN; ASTEC
Keywords: Ruthenium; Primary circuit; Severe accident; Phébus FP; CFD/FLUENT; ASTEC;
CESAM - Code for European severe accident management, EURATOM project on ASTEC improvement
Keywords: SAM; ASTEC; Severe accident simulation; CESAM FP7;
Benchmark exercise TH-27 on natural convection with steam injection and condensation inside the extended THAI facility
Keywords: Thermohydraulic benchmark; Natural convection; Containment test facility; THAI+; ASTEC; COCOSYS; MELCOR; GASFLOW; CFD;
Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2.0
Keywords: 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
Validation of ASTECV2.1 based on the QUENCH-08 experiment
Keywords: FRS; Fuel Rod Simulator; LWR; Light Water Reactor; NPP; Nuclear Power Plant; SAM; Severe Accident Management; SAMGs; Severe Accident Management Guidelines; Zry; Zircaloy; Code validation; Severe accident; ASTEC; QUENCH; Reflooding;
Analysis of primary bleed and feed strategies for selected SBLOCA sequences in a German Konvoi PWR using ASTEC V2.0
Keywords: 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
Evaluation of JRC source term methodology using MAAP5 as a fast-running crisis tool for a BWR4 Mark I reactor
Keywords: 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
Application of Best Estimate Approach for Modelling of QUENCH-03 and QUENCH-06 Experiments
Keywords: ASTEC; Best estimate approach; RELAP/SCDAPSIM; QUENCH
Simulation of the ICE P1 test for a validation of COCOSYS and ASTEC codes
Keywords: Ingress-of-coolant event; Nuclear fusion facility; COCOSYS; ASTEC
Plant application of ICARE/ASTECv2.0r3 computer code for investigation of in-vessel melt retention in VVER-1000 reactor design
Keywords: ASTEC; Accident Source Term Evaluation Code; HF; heat flux; ICARE; module of ASTEC computer code; IVMR; in-vessel melt retention; NPP; nuclear power plant; RPV; reactor pressure vessel; SAM; Severe Accident Management; SBO; station blackout; VVER1000; wat
The integral analysis of 40 mm diameter pipe rupture in cooling system of fusion facility W7-X with ASTEC code
Keywords: ASTEC; W7-X; LOCA
Investigation of molten core-concrete interaction reactor benchmark test for VVER 1000
Keywords: 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
Modeling of AP1000 and simulation of 10-inch cold leg small break LOCA using the CESAR thermal-hydraulic module of ASTEC
Keywords: AP1000; Small break LOCA; ASTEC; Numerical simulation; Passive safety systems
PWR Medium Break LOCA source term analysis using ASTEC code
Keywords: ASTEC; Medium Break LOCA; PWR; Source term;
Analysis of the THAI Iod-11 and Iod-12 tests: Advancements and limitations of ASTEC V2.0R3p1 and MELCOR V2.1.4803
Keywords: AECL; Atomic Energy of Canada Limited; CSNI; Committee on the Safety of Nuclear Installations; FPC; Fission Product Chemistry; EU; European Union; GRS; Gesellschaft für Anlagen- und Reaktorsicherheit; IP; Iodine Pool; IRSN; Institut de Radioprotection et
Metal oxide aerosol dry deposition in laminar pipe flow at high thermal gradients and comparison with SOPHAEROS module of ASTEC reactor accident analysis code
Keywords: Aerosol; Deposition; Laminar flow; Thermophoresis; SOPHAEROS; ASTEC;
Synthesis of the ASTEC integral code activities in SARNET - Focus on ASTEC V2 plant applications
Keywords: ASTEC; Severe accident; Simulation; Scenario; SARNET; Severe accident management;
ASTECv2/MEDICIS computer code investigation of influence of water content and carbon dioxide content in the concrete on the kinetics of molten corium-concrete interaction
Keywords: ASTEC; severe accident computer code; GEMINI2; code for physic-chemistry calculation; JPA; joint program activity; MCCI; molten core concrete interaction; NUCLEA 09; thermo-dynamic database; NPP; nuclear power plant; SARNET2; severe accident research Euro
Fission product release from nuclear fuel II. Validation of ASTEC/ELSA on analytical and large scale experiments
Keywords: ASTEC, accident source term evaluation code; FP, fission product; PWR, pressurised water reactor; SM, structural materialSevere accident; Fission product release; ASTEC
ASTEC V2.0 computational evaluation of source term and its chemical forms under accidental conditions during mid-loop operation
Keywords: Mid-loop operation; Severe Accident; Source term; Air ingress; PWR; ASTEC
ASTEC V1.3 code SOPHAEROS module validation using the STORM experiments
Keywords: ASTEC; STORM; SOPHAEROS; Resuspension; Deposition; Aerosol