Estimation of resonance self-shielding effect in PWR pin cell for different fuel types
Keywords: Self-shielding effect; Subgroup method; Equivalence in dilution; PWR;
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Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part I Bamboo-Lattice
Keywords: PWR; NECP-Bamboo; Bamboo-Lattice; BEAVRS; 2D whole-core one-step calculation;
Seismic analysis of PWR control rod drop with the CRDAC scram performance code
Keywords: Scram time; PWR; SSE; Control rod drop; CRDAC;
Systematic hydrogen risk analysis of OPR1000 containment before RPV failure under station blackout scenario
Keywords: AACDGS; Alternate AC Diesel Generator System; AICC; Adiabatic Isochoric Complete Combustion; CDF; Core Damage Frequency; CEDM; Control Element Drive Mechanism; CFD; Computational Fluid Dynamics; CSS; Containment Spray System; CV; Control Volume; DBA; Desi
Expansion of nuclear power technology to new countries - SMRs, safety culture issues, and the need for an improved international safety regime
Keywords: CDF; core damage frequency; CNS; Convention on Nuclear Safety; FSP; fundamental safety principles; IAEA; International Atomic Energy Agency; IDC; interest during construction; LR; large reactor; LWR; light water reactor; MW; megawatt; MWe; megawatt-electr
Numerical investigation of in-vessel core coolability of PWR through an effective safety injection flow model using MELCOR simulation
Keywords: 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
Acceleration of the exponential function expansion nodal SP3 method by multi-group GMRES algorithm for PWR pin-by-pin calculation
Keywords: PWR; Pin-by-pin; EFEN; Wielandt shift algorithm; Multi-group GMRES algorithm;
Severe accident management measures for a generic German PWR. Part I: Station blackout
Keywords: Severe accident; Station blackout; PWR; Konvoi; Accident management;
Boundary identification between LBLOCA and SBLOCA based on stratification and temperature gradient in two-phase PTS
Keywords: 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
Correlation of microstructure and stress corrosion cracking initiation behaviour of the fusion boundary region in a SA508 Cl. 3-Alloy 52M dissimilar weld joint in primary pressurized water reactor environment
Keywords: ASTM E8/E8M-16a; standard test methods for tension testing of metallic materials; CSL; coincidence site lattice; DH; dissolved hydrogen; DO; dissolved oxygen; DZ; dilution zone; EBSD; electron backscatter diffraction; EDX; energy dispersive x-ray; FB; fus
Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core
Keywords: PWR; Nuclear design; NECP-Bamboo; Bamboo-Core; BEAVRS;
Improvement of plant reliability based on combination of prediction and inspection of wall thinning due to FAC
Keywords: 1-3D; one- to three-dimensional; AC; alternating current; AESJ; Atomic Energy Society of Japan; AT; acoustic emission testing; BWR; boiling water reactor; CBM; condition-based maintenance; CFD; computational fluid dynamics; CF; corrosion fatigue; CS; carb
ROSA/LSTF test and RELAP5 code analyses on PWR hot leg small-break LOCA with accident management measure based on core exit temperature and PKL counterpart test
Keywords: PWR; ROSA/LSTF; Small-break LOCA; Accident management; Core exit temperature; Counterpart test; RELAP5 code;
Droplets entrainment ratio in a PWR hot-leg pipe geometry
Keywords: PWR; Hot-leg; CCFL mechanisms; Droplets entrainment ratio; Empirical correlation; CFD validation data;
Derivation of radiological source term of Korean Design System-Integrated Modular Advanced ReacTor (SMART)
Keywords: SMART; CHASNUPP-1; KORI-1; PWR; Source term; Fission products; Coolant inventory;
Demonstration of LOTUS multiphysics BEPU analysis framework for LB-LOCA simulations
Keywords: BA; Burnable Absorber; BEPU; Best Estimate Plus Uncertainty; BOC; Beginning of Cycle; CASL; Consortium for Advanced Simulation of Light Water Reactors; CD-A; Core Design-Automation; CD-O; Core Design-Optimization; CFD; Computational Fluid Dynamics; CRAM;
Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations
Keywords: BEPU; best estimate plus uncertainty; CASL; consortium for advanced simulation of light water reactors; CIPS; crud induced power shift; CD-A; core design automation; CD-O; core design optimization; COBRA-TF; coolant-boiling in rod arrays-two fluids; FOM;
Severe accident management measures for a generic German PWR. Part II: Small-break loss-of-coolant accident
Keywords: 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
Sensitivity analysis of VERA-CS and FRAPCON coupling in a multiphysics environment
Keywords: BEPU; Best Estimate Plus Uncertainty; CASL; Consortium for Advanced Simulation of Light Water Reactors; CD-A; Core Design Automation; CD-O; Core Design Optimization; COBRA-TF; Coolant-Boiling in Rod Arrays-Two Fluids; EOC; End Of Cycle; FOM; Figure Of Mer
Neutron noise observations in German KWU built PWRs and analyses with the reactor dynamics code DYN3D
Keywords: APSD; Auto-Power Spectral Density; CCF; Cross Correlation Function; FA; Fuel Assembly; FFT; Fast Fourier Transformation; LFNS; Low Frequency Neutron Noise; LHR; Linear Heat Rate; NRMS; Normalized Root Mean Square; PWR; Pressurized Water Reactor;
Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
Keywords: Accident Management; Core Exit Temperature; Integral Test Facility; Peak Cladding Temperature; PKL; Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility); PWR; Station Blackout; TRACE; Validation;
Phenomenology of BWR fuel assembly degradation
Keywords: Phenomenology; Fuel degradation; BWR; Control blade; Channel box; Phase diagram; U-Zr-O system; UO2-Zry system; B4C-Stainless steel system; B4C/SS-Zry system; Eutectic interaction model; Hydrogen uptake in Zry; B4C oxidation; Fukushima-daiichi nuclear pow
Statistical error propagation in HTR burnup model
Keywords: BPR; Burnable Poison Rod; BWR; Boiling Water Reactor; EFPD; Equivalent Full Power Days; HTR; High Temperature Reactor; keff; effective neutron multiplication factor; MC; Monte Carlo; MCB; continuous energy Monte Carlo burnup (code); MCNP; Monte Carlo N-Pa
Application of the BEPU methodology to assess fuel performance in dry storage
Keywords: BE; best estimate; BEPU; Best Estimate Plus Uncertainty; CHS; cladding hoop stress in dry storage (MPa); EOL; end-of-reactor-life; FGR; fission gas release; NRC; Nuclear Regulatory Commission; PDF; probabilistic distribution function; PNNL; Pacific Northw
Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores
Keywords: Bowing effects; Isotope inventory; Assembly bow; CASMO-5; SERPENT-2; Full core simulation; PWR;
EELS and electron diffraction studies on possible bonaccordite crystals in pressurized water reactor fuel CRUD and in oxide films of alloy 600 material
Keywords: Alloy 600; AOA; Bonaccordite; CIPS; EDS; EELS; Electron Diffraction; FIB; Fuel CRUD; Oxide Film; PWR; TEM;
New calculation method for PWR control rod assemblies with APOLLO3®
Keywords: APOLLO3®; V&V; PWR; Control Rod;
Determinants and considerations of Rosatom's external strategy
Keywords: 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;
Feasibility to convert an advanced PWR from UO2 to a mixed U/ThO2 core - Part I: Parametric studies
Keywords: Thorium; PWR; AP1000; Neutronics;
Design of a CFD scheme using multiple RANS models for PWR
Keywords: CFD; RANS; PWR; Hybrid application;
Station black out concurrent with PORV failure using a Generic Pressurized Water Reactor simulator
Keywords: AFAS-T; Auxiliary Feed Water Actuation for Turbine-driven Pump; AFW; Auxiliary Feed Water System; APR-1400; Advanced Pressurized Water Reactor (1400 rated power MWe); CCF; Common Cause Failure; DG; Diesel Generator; ETA; Event Tree Analysis; FLC; Factored
Analysis of the equipment and instrumentation qualification criteria using 3D containment models
Keywords: Environmental Qualification; Containment; GOTHIC; PWR; Safety analysis; DBA;
Enhancements to the Nodal Drift Method for a Rod Ejection Accident in a PWR-like mini-core with lumped thermal model
Keywords: Nodal Drift Method; Spatial kinetics; Diffusion theory; Rod Ejection Accident; PWR; Lumped thermal model;
Image-processing of time-averaged interface distributions representing CCFL characteristics in a large scale model of a PWR hot-leg pipe geometry
Keywords: PWR; Hot-leg; CCFL characteristics; Time-averaged interface distribution; CFD validation data; Two-phase flows; Complex geometry; SBLOCA;
Numerical modelling of a direct contact condensation experiment using the AIAD framework
Keywords: CFD; CMFD; Horizontal flow; PTS; PWR; AIAD; DCC; Two-phase flow; Two fluid flow;
Quantification of history effects in PWR modelling
Keywords: Cross section preparation; PWR; Control rods; History effects;
Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles
Keywords: CASMO-5; SIMULATE-3; SHARK-X; Uncertainty propagation; PWR;
Sensitivity Analysis of the Galerkin Finite Element Method Neutron Diffusion Solver to the Shape of the Elements
Keywords: Galerkin Finite Element Method; Shape Function; Triangle; Quadrilateral; Linear; Second Approximation; GFEM; Galerkin Finite Element Method; IAEA; International Atomic Energy Agency; BC; Boundary Condition; RPE; Relative Percent Error; PWR; Pressurized Wa
Evaluation of cooling capacity with more fuel stored in the spent fuel pool of the Kuosheng plant
Keywords: BWR; boiling water reactor; CLP; cask loading pool; FSAR; Final Safety Analysis Report; FSB; Fuel Storage Building; HX; heat exchanger; OLTP; original licensed thermal power; PWR; pressurized water reactor; RHR; Residual Heat Removal; SFP; spent fuel pool
Development of a feed-and-bleed operation strategy with hybrid-SIT under low pressure condition of PWR
Keywords: APR+; (advanced power reactor plus); CCF; (common cause failure); CDF; (core damage frequency); CET; (core exit temperature); CSP; (containment spray pump); EOP; (emergency operating procedure); F&B; (feed and bleed); HEP; (human error probability); H-SIT
Neutronic predictors for PWR fuelled with multi-recycled plutonium and applications with the fuel cycle simulation tool CLASS
Keywords: Fuel cycle simulations; PWR; Plutonium multi-recycling; Fuel loading model; Neural network;
Verification of AP1000® low-margin PRA sequences based on best-estimate calculations
Keywords: ACC; Accumulator; ADS; Automatic Depressurization System; BE; Best-Estimate; BS; Bounding Sequence; CDF; Core Damage Frequency; CMT; Core Make-up Tank; DSA; Deterministic Safety Analysis; DVI; Direct Vessel Injection; DVILB; Direct Vessel Injection Line B
Fission products and nuclear fuel behaviour under severe accident conditions part 1: Main lessons learnt from the first VERDON test
Keywords: LWR; PWR; VERDON tests; HEVA-VERCORS tests; Severe accidents; Fission product behaviour; Fission product releases;
Developing and analyzing long-term fuel management strategies for an advanced Small Modular PWR
Keywords: SMR; PWR; Fuel management; Core; Safety; Equilibrium;
An extended BEPU approach integrating probabilistic assumptions on the availability of safety systems in deterministic safety analyses
Keywords: BEPU, EBEPU; Probabilistic and deterministic safety analysis; Option 4; Realistic configurations; Safety systems; AFWS; Auxiliary Feed Water System; ATWS; Anticipated Transient Without Scram; BE; Best Estimate; BEPU; Best Estimate Plus Uncertainty methodo
Accelerated corrosion and oxide dissolution in 316L stainless steel irradiated in situ in high temperature water
Keywords: Stainless steel; Radiation; Irradiation effects; Radiolysis; Passivity; Passive films; Raman spectroscopy; STEM; PWR;
Grid-to-rod flow-induced impact study for PWR fuel in reactor
Keywords: PWR; Flow-induced impact; Grid-to-rod dynamic contact;
Recent advances in accurate neutronic calculation of GEN-3 LWR reactors
Keywords: PWR; GEN-III; APOLLO2; EOLE reactor; Uncertainty calculation;
Loss of Coolant Accident in Pressurized Water Reactor. Prediction of a 6-inch Cold Leg Break with Relap5 and Cathare 2
Keywords: RELAP5; CATHARE2; PWR; IB-LOCA; Nuclear Safety;
CFD simulation for the optimal design and utilization of experiment to research the flow process in PWR
Keywords: CFD; Optimal design; Experiment; PWR;