Keywords: BWR، راکتور آب جوش; BC, boiling channel; BWR, boiling water reactor; DWO, density wave oscillation; FFT, fast Fourier transform; HBM, harmonic balance method; HEM, homogeneous equilibrium model; MNS, moving nodal scheme; MSB, marginal stability boundary; NMPC, nonlinear mode
مقالات ISI BWR، راکتور آب جوش (ترجمه نشده)
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Keywords: BWR، راکتور آب جوش; BWR, boiling water reactor; LAS, low alloy steel; SCC, stress corrosion cracking; FB, fusion boundary; HAZ, heat-affected zone; GB, grain boundary; IG, intergranular; AFM, atomic force microscope; APT, atom probe tomography; CBB, creviced bent beam; BM, b
Keywords: BWR، راکتور آب جوش; BWR, boiling water reactor; CSS, containment spary system; DBA, design basis accident; ECCS, emergency core cooling system; GSI, generic safety issue; LOCA, loss-of-coolant accident; LWR, light water reactor; MPP, mesh-added perforated plate; NPSH, net po
Keywords: BWR، راکتور آب جوش; ABWR, advanced boiling water reactor; AGR, advanced gas-cooled reactor; BWR, boiling water reactor; DOE, Department of Energy (USA); GCR, gas-cooled reactor; GEN, generation; GFR, gas fast reactor; HTHL, high temperature helium loop; HTR, high temperature
Accident mitigation for spent fuel storage in the upper pool of a Mark III containment
Keywords: BWR، راکتور آب جوش; BWR, Boiling Water Reactor; FSAR, Final Safety Analysis Report; HVAC, Heating, Ventilating, and Air Conditioning; PCT, peak cladding temperature; PWR, Pressurized Water Reactor; RB, reactor building; RHR, Residual Heat Removal; SFP, spent fuel pool; STGS,
Main modelling features of the ASTEC V2.1 major version
Keywords: BWR، راکتور آب جوش; ASTEC, Accident Source Term Evaluation Code; BARC, Bhabha Atomic Research Centre, India; BIP, Behaviour of Iodine Project; BWR, Boiling Water Reactor; CATHARE, Code Avancé de THermohydraulique pour les Accidents sur les Réacteurs à Eau; CCI, corium concre
Study on heat removal capability of calandria vault water from molten corium in calandria vessel during severe accident of a PHWR
Keywords: BWR، راکتور آب جوش; BWR, boiling water reactor; CANDU, CANada Deuterium Uranium; CHF, critical heat flux; CV, cylindrical vessel; FE, finite element; FEM, finite element method; FOREVER, Failure Of REactor VEssel Retention; IAEA, International Atomic Energy Agency; LHF, lowe
Numerical investigation on practicability of reducing MCST by using grid spacer in a tight rod bundle
Keywords: BWR، راکتور آب جوش; SCWR, supercritical pressure water cooled reactor; PWR, pressurized water reactor; BWR, boiling water reactor; CFD, computational fluid dynamics; HFDVs, hydrodynamically fully-developed values; MCST, maximum cladding surface temperature
Thermal-hydraulics and safety concepts of supercritical water cooled reactors
Keywords: BWR، راکتور آب جوش; ADS, automatic depressurization system; BWR, boiling water reactor; CFD, computational fluid dynamics; DNS, direct numerical simulation; HDR, heissdampfreaktor; HPLWR, high performance light water reactor; PWR, pressurized water reactor; SCWR, supercritic
Significance of Phébus-FP results for plant safety in Switzerland
Keywords: BWR، راکتور آب جوش; BWR, boiling water reactor; CFVS, Containment Filtered Venting Systems; ENSI, Eidgenössisches Nuklearsicherheitinspektorat (Federal Nuclear Safety Inspectorate); IRSN, institut de radioprotection et de sûreté nucléaire (institute for radiological protecti
Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis
Keywords: BWR، راکتور آب جوش; AGR, Advanced Gas-cooled Reactor; BWR, boiling water reactor; EOL, end of life; FGR, fission gas release; FUMEX, Fuel Modelling at Extended Burn-up; IAEA, International Atomic Energy Agency; IFPE, International Fuel Performance Experiments; LWR, light wat
Optimizing the performance of cold-neutron tomography for investigating annular flows and functional spacers in fuel rod bundles
Keywords: BWR، راکتور آب جوش; AC-110, Anticorodal 110; BWR, boiling water reactor; CCD, charge coupled device; CHF, critical heat flux; ESF, edge spread function; FBP, filtered back projection; FWHM, full width at half maximum; FOV, field of view; ICON, imaging with cold neutrons; LFT
Experimental investigations of droplet carryover from the separator drum of an air-lift loop simulating a scaled-down AHWR
Keywords: BWR، راکتور آب جوش; Entrainment; Carryover; Air-lift loop; Scaling analysis; AHWRAHWR, Advanced Heavy Water Reactor; BWR, Boiling Water Reactor; FAD, Free Air Delivery; NCL, Natural Circulation Loop; PWR, Pressurized Water Reactor
Modeling of BWR Inter-Ramp Project experiments by means of TRANSURANUS code
Keywords: BWR، راکتور آب جوش; AR, after ramp; BIRP, BOCA Inter-Ramp Project; BOCA, Boiling Capsule; BWR, Boiling Water Reactor; BWR-IR, BWR Inter-Ramp Project; Cd, Cadmium; CL, Conditioning Level; CRP, Coordinate Research Program; Cs, cesium; DIMNP, Dipartimento di Ingegneria Meccanic
Food safety regulations: what we learned from the Fukushima nuclear accident
Keywords: BWR، راکتور آب جوش; Emergency exposure situation; Existing exposure situation; Food safety regulation; Fukushima nuclear accident; Graded triphasic reference level; Internal radiation exposureBSS, International Basic Safety Standards; BWR, Boiling water reactor; CAC, Codex A
Radiation-induced degradation of stainless steel light water reactor internals
Keywords: BWR، راکتور آب جوش; ASTM, American Society for Testing and Materials; BOR, series of Russian reactors (e.g., BOR-60); BWR, boiling water reactor; CGR, crack growth rate; DOE, United States Department of Energy; dpa, displacements per atom; EBR-II, Experimental Breeder Reacto
Time-domain linear and non-linear studies on density wave oscillations
Keywords: BWR، راکتور آب جوش; ATHLET, analysis of thermal-hydraulics of leaks and transients; ATWS, anticipated transient without scram; BWR, boiling water reactor; DFM, drift-flux model; DWO, density wave oscillation; HEM, homogeneous equilibrium model; IRI, Interfaculty Reactor Inst
European supercritical water cooled reactor
Keywords: BWR، راکتور آب جوش; BWR, boiling water reactor; CEA, Commissariat à l’Energie Atomique; CFD, computational fluid dynamics; GIF, Generation IV International Forum; HP, high pressure; HPLWR, high performance light water reactor; IP, intermediate pressure; JRC, Joint Research C
Validation of CATHARE V2.5 thermal-hydraulic code against full-scale PERSEO tests for decay heat removal in LWRs
Keywords: BWR، راکتور آب جوش; AP600, Advanced Plant 600; BWR, Boiling Water Reactor; CATHARE, Code for Analysis of THermalhydraulic during an Accident of Reactor and safety Evaluation; CEA, Commissariat à l’Énergie Atomique; CFD, Computational Fluid Dynamics; ENEA, Agenzia Nazionale p
Analysis of different containment models for IRIS small break LOCA, using GOTHIC and RELAP5 codes
Keywords: BWR، راکتور آب جوش; AB, Auxiliary building; ADS, Automatic depressurization system; AP600, Advanced pressurized reactor – 600 MWe; AP1000, Advanced pressurized reactor – 1000 MWe; BWR, Boiling water reactor; CVCS, Chemical volume and control system; DD, Droplets diameter; DV
PERFORM 60: Prediction of the effects of radiation for reactor pressure vessel and in-core materials using multi-scale modelling – 60 years foreseen plant lifetime
Keywords: BWR، راکتور آب جوش; AKMC, atomistic kinetic Monte Carlo; AFTM, Advanced Fracture Toughness module; ASME, American Society of Mechanical Engineers; BWR, boiling water reactor; CP, crystal plasticity; DD, dislocation dynamics; DDD, discrete dislocation dynamics; DFT, density f
A review on the clad failure studies
Keywords: BWR، راکتور آب جوش; BCC, body-centered cubic structure; BDBA, beyond design basis accident; BWR, boiling water reactor; CHF, critical heat flux; DNB, departure from nucleate boiling; ECCS, emergency core cooling system; GWD, giga Watt per day; HCP, hexagonal closed packed st
Thermal consideration of CANDU-SCWR sliding pressure startup through subchannel analysis
Keywords: BWR، راکتور آب جوش; ATHAS, advanced thermal-hydraulics analysis subchannel; BWR, boiling water reactor; CANDU, CANada Deuterium Uranium; CHF, critical heat flux; FPP, fossilfired power plant; LWR, light water reactor; PDO, post-dry out; PHWR, pressurized heavy water reactor;
Mass flow rate sensitivity and uncertainty analysis in natural circulation boiling water reactor core from Monte Carlo simulations
Keywords: BWR، راکتور آب جوش; ABWR, advanced boiling water reactor; BWR, boiling water reactor; BREST, NPP with a lead-cooled fast reactor fuelled with uranium–plutonium; CAREM, advanced PWR; ESBWR, economic simplified boiling water reactor; FUJI, Japanese molten-salt reactor (MSR) co
Integral analysis of large LOCA beyond design basis accident scenario in RBMK-1500
Keywords: BWR، راکتور آب جوش; ALS, accident localisation system; BDBA, beyond design basis accident; BSRC, bottom steam reception chamber; BWR, boiling water reactor; CTCS, condenser tray cooling system; ECCS, emergency core cooling system; FC, fuel channel; FP, fission products; GDH,
A review of integration strategies for solid oxide fuel cells
Keywords: BWR، راکتور آب جوش; APU, auxiliary power unit; ASU, air separation unit; AR, absorption refrigeration; BoP, balance of plant; BWR, boiling water reactor; CHP, combined heat and power; COE, cost of electricity; CB, combustor; CP, compressor; GT, gas turbine; HE, heat exchange
Assessment of thermal aging embrittlement in a cast stainless steel valve and its effect on the structural integrity
Keywords: BWR، راکتور آب جوش; ANL, Argonne National Laboratory; ASME, American Society of Mechanical Engineers; BWR, boiling water reactor; CDF, crack driving force; EPRI, Electric Power Research Institute; MOV, motor operated valve; NRC, U.S. Nuclear Regulatory Commission; RT, room t
Two types of a passive safety containment for a near future BWR with active and passive safety systems
Keywords: BWR، راکتور آب جوش; ABWR, advanced boiling water reactor; ACCS, advanced corium cooling system; AFC, active fuel cladding; AOT, allowable operable time; BIPSS, build-in passive safety systems; BWR, boiling water reactor; CCFP, conditional containment failure probability; CDF
Steady state thermal-hydraulic analysis of hydride-fueled grid-supported BWRs
Keywords: BWR، راکتور آب جوش; ABWR, advanced boiling water reactor; BC, best case; BU, burnup; BWR, boiling water reactor; CB, control blade design; CCCR, corner cruciform control rod design; CHF, critical heat flux; CHFR, critical heat flux ratio; CPR, critical power ratio; DR, decay
Effect of corrosion potential on the corrosion fatigue crack growth behaviour of low-alloy steels in high-temperature water
Keywords: BWR، راکتور آب جوش; BWR, boiling water reactor; C(T), compact tension (specimen); CF, corrosion fatigue; CGR, crack growth rate; CT, crack-tip; ΔK, ΔK = KImax − KImin: total stress intensity factor range; DCPD, direct current potential drop (method); DO, dissolved oxygen; DS
Approach to accident management in RBMK-1500
Keywords: BWR، راکتور آب جوش; AFWP, auxiliary feedwater pump; ALS, accident localisation system; BDBA, beyond design basis accident; BRU-B, Valve for steam discharge to ALS (Russian abbreviation); BSRC, bottom steam reception chamber; BWR, boiling water reactor; CTCS, condenser tray c
Environmentally-assisted cracking behaviour in the transition region of an Alloy182/SA 508 Cl.2 dissimilar metal weld joint in simulated boiling water reactor normal water chemistry environment
Keywords: BWR، راکتور آب جوش; ANL, Argonne National Laboratory; BWM, bulk weld metal; BWR, boiling water reactor; CGR, crack growth rate; C(T), compact tension (specimen); DCPD, direct current potential drop (method); DLZ, dilution zone; DO, dissolved oxygen; DSA, dynamic strain agein
Corrosion fatigue crack growth behaviour of low-alloy reactor pressure vessel steels under boiling water reactor conditions
Keywords: BWR، راکتور آب جوش; BWR, boiling water reactor; C(T), compact tension (specimen); CF, corrosion fatigue; CGR, crack growth rate; ΔK, ΔK=KImax-KImin: total stress intensity factor range; DCPD, direct current potential drop (method); DH, dissolved hydrogen; DO, dissolved oxyge
Development and testing of RBMK-1500 model for BDBA analysis employing RELAP/SCDAPSIM code
Keywords: BWR، راکتور آب جوش; ALS, accident localisation system; BDBA, beyond design basis accident; BWR, boiling water reactor; DS, drum separator; ECCS, emergency core cooling system; FC, fuel channel; GDH, group distribution header; LEI, lithuanian energy institute; LOCA, loss-of-c
Review and proposal for best fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations
Keywords: BWR، راکتور آب جوش; BWR, boiling water reactor; DHRS, decay heat removal system; ETDR, experimental technology demonstration reactor; FA, fuel assembly; FM, flow meter; GCFR, gas cooled fast reactor; HX, heat exchanger; LBE, lead–bismuth eutectic; LWR, light water reactor; P
A study on the boron injection initiation temperature curve of BWR
Keywords: BWR، راکتور آب جوش; APRMs, average power range monitoring system; ATWS, anticipated transient without scram; BIIT, boron injection initiation temperature; BWR, boiling water reactor; BWROG, boiling water reactor owners’ group; EOP, emergency operating procedure; FQdh-10, dec
Model extension and improvement for simulator-based software safety analysis
Keywords: BWR، راکتور آب جوش; ACE, abnormal conditions and events; ABWR, advanced boiling water reactor; ARI, alternate rod insertion; BWR, boiling water reactor; CMF, common mode failure; CPU, central processing unit; FMEA, failure modes and effects analysis; FWP, feedwater pump; FTA
RELAP5/MOD3.2 sensitivity calculations of loss-of-feed water (LOFW) transient at Unit 6 of Kozloduy NPP
Keywords: BWR، راکتور آب جوش; AFWP, auxiliary feed water pump; AKHP, Russian abbreviation of “Automatic Control for Neutron Flux”; ANL, Argonne National Laboratory; BRU-A, steam dumping devise to the atmosphere; BRU-K, steam dumping devise to the condenser; BWR, boiling water reactor;
Validation and application of the WABE code: Investigations of constitutive laws and 2D effects on debris coolability
Keywords: BWR، راکتور آب جوش; BWR, boiling water reactor; CCFL, counter-current flow limitation; DHF, dryout heat flux; LWR, light water reactor; PWR, pressurized water reactor; RPV, reactor pressure vessel