The ultimate response guideline simulation and analysis using TRACE, MAAP5, and FRAPTRAN for the Chinshan Nuclear Power Plant
Keywords: TRACE; MAAP5; FRAPTRAN; BWR; Safety analysis;
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Application of the FRI crack growth model for neutron-irradiated stainless steels in high-temperature water of a boiling water reactor environment
Keywords: BWR; boiling water reactor; CGR; crack growth rate; CT; compact tension; EPR; electrochemical potentiokinetic reactivation; FRI; fracture and reliability research institute at Tohoku University; GB; grain boundary; IASCC; irradiation assisted stress corro
Optimization of axial enrichment distribution for BWR fuels using scoping libraries and block coordinate descent method
Keywords: Axial enrichment distribution; BWR; Scoping libraries; Block coordinate descent method; Enrichment difference parameter;
Hydrogen distribution and Passive Autocatalytic Recombiner (PAR) mitigation in a PWR-KWU containment type
Keywords: AECL; Atomic Energy of Canada Limited (Canada); BWR; Boiling Water Reactor; CFD; Computational Fluid Dynamics; COCOSYS; Containment Code System; CSN; Consejo de Seguridad Nuclear (Spanish Nuclear Safety Council); DLL; Dynamic Linked Library; EPR; European
Heat up and failure of BWR upper internals during a severe accident
Keywords: Upper internals; BWR; Severe accident; MELCOR;
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
Decay Ratio estimation in BWRs based on the improved complete ensemble empirical mode decomposition with adaptive noise
Keywords: Empirical mode decomposition; Mode mixing; BWR; Instantaneous frequency; Decay Ratio;
Oxide evolution on Alloy X-750 in simulated BWR environment
Keywords: High temperature water; Alloy X-750; Corrosion; NiFe2O4; Oxide formation; BWR; Nickel based alloys;
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
Prediction of 3D nuclear reactor's operational parameters from 2D fuel lattice design information: A data mining approach
Keywords: BWR; Reactor simulation; Data mining;
Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K
Keywords: BWR; Oskarshamn-2; Feedwater transient; Stability; SIMULATE-3K;
MELCOR 2.1 analysis of melt behavior in a BWR lower head during LOCA and SBO accident
Keywords: Melt behavior; BWR; MELCOR; LOCA; SBO
A statistical analysis in the BWR fuel lattice design
Keywords: BWR; Nuclear fuel; Statistical analysis
OECD/NEA Sandia Fuel Project phase I: Benchmark of the ignition testing
Keywords: ATHLET-CD; Analysis of THermal-hydraulics of LEaks and Transients with Core Degradation; BIC; boundary and initial conditions; BWR; boiling water reactor; CFD; computational fluid dynamics; CYBL; Cylindrical Boiling; ID; inner diameter; LOCA; loss of cool
Using Largest Lyapunov Exponent to Confirm the Intrinsic Stability of Boiling Water Reactors
Keywords: Attractor; BWR; Instability; Large Lyapunov Exponent; Limit Cycle
Estimation of a boundary to distinguish between radioactive materials and non-radioactive materials around a Main Steam line and a Feed Water line in a Biological Shielding Wall of a BWR for decommissioning
Keywords: Decommissioning; BWR; Main Steam line; Non-radioactive (NR) boundary; Activation foil measurement; Neutron-streaming; Coupling technique; Directional mesh set; DOORS; TORT; SCALE6.1; ORIGEN-S; COUPLE;
Parametric studies of the PWR fuel assembly modeling with Monte-Carlo method
Keywords: BOL; beginning-of-life; BWR; Boiling Water Reactor; CFD; Computational Fluid Dynamics; CRAM; Chebyshew Rational Approximation Method; ENDF; Evaluated Nuclear Data File; EOL; end-of-life; FA; fuel assembly; FIMA; Fissions per Initial Metal Atom; HTR; High
AGENT-TH scheme: New thermal hydraulics (TH) code coupled with the AGENT neutronics code for light water reactors modeling and analysis
Keywords: AGENT; Drift flux model; Homogeneous equilibrium mixture (HEM) model; Method of characteristics; PWR; BWR
The influence of ppb levels of chloride impurities on the strain-induced corrosion cracking and corrosion fatigue crack growth behavior of low-alloy steels under simulated boiling water reactor conditions
Keywords: AL; action level of EPRI water chemistry guidelines; ASTM; American Society of Testing and Materials Standards; ASTM E399; test method for plane-strain fracture toughness of metallic materials; BWR; boiling water reactor; CF; corrosion fatigue; CL; consta
Influence of void fraction on BWR spent fuel direct recycling scenario
Keywords: BWR; Void fraction; Spent fuel; Direct recycling; SUPEL scenario
Comparative study of the hydrogen generation during short term station blackout (STSBO) in a BWR
Keywords: Several accident NPP; BWR; Short-term SBO; MELCOR; SCDAP/RELAP5;
Negative pressure difference evaluation of Lungmen ABWR containment by using GOTHIC
Keywords: 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
A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments
Keywords: 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;
Small and Medium sized Reactors (SMR): A review of technology
Keywords: 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
Searching for enrichment and gadolinia distributions in BWR fuel lattices through a Heuristic-Knowledge Method
Keywords: Fuel lattice design; Heuristic-Knowledge Method; BWR;
BWR Mark III containment analyses using a GOTHIC 8.0 3D model
Keywords: GOTHIC; Containment; Mass and energy release; LOCA; SBO; BWR;
Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr-10Ni-Ti austenitic stainless steels
Keywords: Stainless steel; Irradiation; Structural changes; Phase composition; Recovery annealing; PVIs; pressure vessel internals; dpa; displacement per atom; NPP; nuclear power plant; TEM; transmission electron microscopy; STEM; scanning transmission electron mic
Thermo-mechanic behavior simulation for fuel assemblies manufactured in Mexico with FEMAXI-VI code
Keywords: BWR; Fuel assemblies; Thermo-mechanical behavior; FEMAXI-VI code
Study the neutronic analysis and burnup for BWR fueled with hydride fuel using MCNPX code
Keywords: BWR; MCNPX; Hydride fuel; Neutronic analysis; UZrH1.6; UThH2
Effects of modeling assumptions on the stability domain of BWRs
Keywords: Stability boundary; BWR; Nuclear coupled thermal–hydraulics; Parametric effects; Uncertainty analysis
ASSERT-PV 3.2: Advanced subchannel thermalhydraulics code for CANDU fuel bundles
Keywords: CANFLEX®; CANadian FLEXible, a registered trademark of AECL and the Korea Atomic Energy Research Institute (KAERI); AECL; Atomic Energy of Canada Limited; AFD; Axial Heat Flux Distribution; ASSERT-PV; Advanced Solution of Subchannel Equations in Reactor
Long-term pressure and temperature analysis and suppression pool mixing of Lungmen ABWR containment
Keywords: 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;
The closed thorium-transuranic fuel cycle in reduced-moderation PWRs and BWRs
Keywords: Thorium; Reduced-moderation; PWR; BWR; Transuranic; Fuel cycle;
Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser
Keywords: ALWR; Advanced Light Water Reactor; BWR; Boiling Water Reactor; DHR; Decay Heat Removal; DLM; Diffusion Layer Model (GOTHIC); DLM-FM; DLM with inclusion of Film roughening and Mist formation effects (GOTHIC); ESBWR; Economic Simplified Boiling Water React
Considerations on the potential use of Nuclear Small Modular Reactor (SMR) technology for merchant marine propulsion
Keywords: ABWR; Advanced Boiling Water Reactor; AECL; Atomic Energy of Canada Ltd.; BWR; Boiling Water Reactor; CRP; Contra Rotating Propeller; C4TX; Centre for Tankship eXcellence; DCNS; Direction Technique des Constructions Navales of France; EFPY; Effective Full
Analyses of the MYRRHA spallation loop using the system code ATHLET
Keywords: ADS; Accelerator Driven System; ATHLET; Analysis of Thermal-hydraulics of Leaks and Transients; BWR; Boiling Water Reactor; CHEOPE; Chemistry Operations; CFD; computational fluid-dynamic; ENEA; Italian National Agency for New Technologies, Energy and Sust
Comparison of metaheuristic optimization techniques for BWR fuel reloads pattern design
Keywords: Fuel reload optimization; Tabu search; Genetic algorithms; Neural networks; Ant colony optimization; BWR
New developments of the MCNP/CTF/NEM/NJOY code system – Monte Carlo based coupled code for high accuracy modeling
Keywords: MCNP5; COBRA-TF; NEM; NJOY; Coupled calculations; BWR
Benchmarking a sub-channel program based on a drift-flux model with 8 × 8 NUPEC BWR rod bundle
Keywords: NUPEC BFBT; BWR; Drift-flux model; Sub-channel analysis; Void fraction
Numerical analysis of hydrogen generation in a BWR during a severe accident
Keywords: Numerical analysis; Hydrogen generation; Nuclear severe accident; Zircaloy oxidation; Reactor shutdown, heat generation; BWR;
Multirecycling of Pu, Am and Cm in BWR
Keywords: Transmutation; Am; Cm; TRU; BWR;
Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests
Keywords: 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
Investigation of global and regional BWR instabilities with a four heated-channel Reduced Order Model
Keywords: BWR; Global and regional instabilities; Reduced Order Models; Core-simulators
Analysis of BWR long-term station blackout accident using TRAC-BF1
Keywords: BWR; Station blackout accident; Fukushima Daiichi; TRAC-BF1
Automatic fuel lattice design in a boiling water reactor using a particle swarm optimization algorithm and local search
Keywords: Lattice design; BWR; Particle swarm optimization; Local search;
Effect of void-fraction on characteristics of several thorium fuel cycles in BWR
Keywords: Thorium fuel; Time-independent burnup; BWR; Void fraction; SRAC 2002
Fuel assembly with inert matrix fuel rods as reload options for Laguna Verde NPP
Keywords: BWR; Inert matrix fuel; Fuel reload
Fuel residence time in BWRs with nitride fuels
Keywords: BWR; Uranium nitride; Enrichment; Fuel cycle; Neutronics
Corrosion fatigue initiation and short crack growth behaviour of austenitic stainless steels under light water reactor conditions
Keywords: ANL; Argonne National Laboratory USA; ASME; American Society of Mechanical Engineers; ASME BPVASME; boiler and pressure vessel code; BWR; boiling water reactor; CF; corrosion fatigue; C(T); compact tension specimen; DCPD; direct current potential drop cra
BWR fuel rod behavior evaluation for preconditioning power ramps with FEMAXI-V
Keywords: BWR; Fuel rod; Thermomechanical behavior; PCI; Preconditioning procedures