CFD simulation for the optimal design and utilization of experiment to research the flow process in PWR
Keywords: CFD; Optimal design; Experiment; PWR;
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Investigation of different burnable absorbers effects on the neutronic characteristics of PWR assembly
Keywords: Burnable absorber; PWR; Gadolinium; Erbium; Dysprosium titanate; Dysprosium hafnate;
Experimental study and numerical simulation of high temperature (1100-1250 °C) oxidation of prior-oxidized zirconium alloy
Keywords: α red; αZr(O) phase formed by reduction of the low temperature oxide layer; Exp; experimental, i.e. data link with experimental results; EKINOX-Zr; Estimation KINetics OXidation numerical model for Zr alloys; HCP; hexagonal close-packed; HT; high temper
System scaling analysis for modeling small break LOCA using the FULL SPECTRUM LOCA evaluation model
Keywords: Top-down scaling; PWR; LOCA; ROSA-IV/LSTF;
Benchmarking of Monte Carlo model of PWR (CNPP-II) core against theoretical and experimental results
Keywords: CNPP-II; PWR; MCNP5; HZP; Excess reactivity; Criticality;
Sensitivity and uncertainty analyses of reactivities for PWR cells with UO2UO2 and MOX fuels
Keywords: Sensitivity; Uncertainty; Self-shielding; Reactivity; PWR
A novel optimization method, Gravitational Search Algorithm (GSA), for PWR core optimization
Keywords: In-core fuel management; Optimization; Gravitational Search Algorithm; Power peaking factor; Multiplication factor; PWR; PARCS code;
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
Best estimate plus uncertainty analysis of departure from nucleate boiling limiting case with CASL core simulator VERA-CS in response to PWR main steam line break event
Keywords: BEPU; best estimate plus uncertainty; CASL; Consortium for Advanced Simulation of Light Water Reactors; CC; correlation coefficient; CFD; computational fluid dynamics; CHF; critical heat flux; CTF; COBRA-TF; DNB; departure from nucleate boiling; DNBR; dep
Localized neutron flux assessment and verification studies using MCNPX PWR full core model
Keywords: PWR; MCNPX; CASMO/SIMULATE; Verification; Neutron fluence; Control rods
On the adoption of carbon dioxide thermodynamic cycles for nuclear power conversion: A case study applied to Mochovce 3 Nuclear Power Plant
Keywords: Nuclear power; Thermodynamic cycle; Carbon dioxide cycle; Supercritical CO2; PWR; Energy conversion;
Station blackout mitigation strategies analysis for Maanshan PWR plant using TRACE
Keywords: Station blackout; PWR; TRACE
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
Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem
Keywords: PWR; EPR; Benchmark;
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
Viability of uranium nitride fueled high-conversion PWR
Keywords: Nitride; Breeder; PWR; High-conversion
Strategy evaluation for fire spray system on Advanced Passive PWR Severe Accident Management Guideline
Keywords: Fire spray system; Severe accident mitigation; Severe Accident Management Guideline; ACC; Accumulator; ADS; Automatic Depressurization System; CA; Computational Aid; CMT; Core Makeup Tank; CSE; Containment Systems Experiment; CSS; Containment Spray System
Reduction of core damage frequency via new design for emergency core cooling system in a typical PWR
Keywords: ECCS; Core damage frequency; PWR; Risk Spectrum
Thermal-hydraulics analysis during fuel element failure in an operating PWR
Keywords: PWR; Fuel element failure; RELAP5; Safety analysis;
Review of the historic neutron noise behavior in German KWU built PWRs
Keywords: Neutron noise; KWU; PWR;
Supra-spinal FAAH is required for the analgesic action of paracetamol in an inflammatory context
Keywords: Paracetamol; FAAH; Analgesia; Brain; AM404; N-(4-Hydroxyphenyl)-5Z,8Z,11Z,14Z-eicosatetraenamide; DMSO; dimethyl sulfoxide; FAAH; fatty acid amide hydrolase; i.c.v.; intracerebroventricular; i.p.; intraperitoneal; i.pl.; intra-plantar; PCR; polymerase cha
Research on the deposition model of particle-like corrosion product in SG tubes of PWR
Keywords: PWR; Particle-like corrosion product; Deposition model; Spring-mass system;
Improving the in situ measurement of RTD response times through Discrete Wavelet Transform in NPP
Keywords: DWT; Discrete Wavelet Transform; RTD; Resistance Temperature Detector; PWR; Pressurized Water Reactor; AR; autoregressive; NPP; Nuclear Power Plant; NRC; Nuclear Regulatory Commission; PSD; Power Spectral Density; MRA; Multi Resolution Analysis; STFT; Sho
A neural network approach for burn-up calculation and its application to the dynamic fuel cycle code CLASS
Keywords: Cross section predictor; PWR; MOX; Neural network; Nuclear scenario;
Study on mitigation of ex-vessel release of fission products in severe accidents for Chinese two loops PWR
Keywords: Severe accident; PWR; Ex-vessel release; Mitigation
Technetium transmutation in thin layer coating on PWR fuel rods
Keywords: Technetium; Transmutation; Thin layer coating; PWR;
Burnup instabilities in the full-core HTR model simulation
Keywords: BOS; beginning of step; BPR; burnable poison rod; CR; control rod; CRAM; Chebyshev Rational Approximation Method; DPA; displacement per atom; EFPD; equivalent full power day; EOS; end of step; HTR; High Temperature Reactor; LWR; Light Water Reactor; MC; M
Sensitivity and uncertainty analysis for UO2 and MOX fueled PWR cells
Keywords: Sensitivity; Uncertainty; IR approximation; Self-shielding; PWR;
Interaction of a peptide derived from C-terminus of human TRPA1 channel with model membranes mimicking the inner leaflet of the plasma membrane
Keywords: ATR-FTIR; attenuated total reflection Fourier transform infrared; CD; circular dichroism; DMPA; dimyristoyl phosphatidic acid; DMPC; dimyristoyl phosphatidylcholine; DMPG; dimyristoyl phosphatidyglycerol; DMPS; dimyristoyl phosphatidylserine; DSC; differe
3-D numerical investigation of water/CuO nanofluid critical heat flux phenomenon in a PWR core channel during LOCA
Keywords: Critical heat flux; Nanoparticle; Two phase flow; 3D; PWR; LOCA;
Advanced plutonium management in PWR, complementarity of thorium and uranium
Keywords: Scenario; Steady-state; Plutonium management; PWR; Thorium
PWR Medium Break LOCA source term analysis using ASTEC code
Keywords: ASTEC; Medium Break LOCA; PWR; Source term;
Investigating the propagation noise in PWRs via closed-loop neutron-kinetic/thermal-hydraulic noise calculations
Keywords: Propagation noise; Neutron-kinetics; Thermal-hydraulics; Noise analysis; PWR; VVER;
Investigation of the ex-core noise induced by fuel assembly vibrations in the Ringhals-3 PWR
Keywords: Ex-core noise; Fuel assembly vibration; Burnup; APSD; PWR;
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;
Comparison of nuclear data uncertainty propagation methodologies for PWR burn-up simulations
Keywords: Uncertainty quantification; Burn-up; PWR; Nuclear data uncertainties; NUDUNA; Hybrid Method;
Static and transient pin-by-pin simulations of a full PWR core with the extended coupled code system DYNSUB
Keywords: DYNSUB; PWR; Coupled code; Local safety parameters; Improved best-estimate; Pin-by-pin simulation;
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
An experimental device to study the revaporisation behaviour of fission product deposits under severe accident conditions
Keywords: Fission products; Caesium; Transport behaviour; Revaporisation; Severe accident; Phébus FP; EDX; energy dispersive X-ray spectroscopy; FPs; fission products; HTR; high-temperature reactor; ICP-MS; inductively coupled plasma mass spectrometry; ITU; Instit
High conversion Th-U233 fuel for current generation of PWRs: Part II - 3D full core analysis
Keywords: High conversion; PWR; Th-U233 fuel; Seed-blanket; DYN3D;
High conversion Th-U233 fuel for current generation of PWRs: Part I - Assembly level analysis
Keywords: High conversion; PWR; Th-U233 fuel; Seed-blanket; DYN3D;
Research on the leak-rate characteristics of leak-before-break (LBB) in pressurized water reactor (PWR)
Keywords: Mathcad; Leak rate; Two-phase critical flow; Friction effect; PWR
An experimental investigation of loop seal clearings in SBLOCA tests
Keywords: ATLAS; Integral effect test; PWR; Loop seal clearing; SBLOCA;
LES analysis of the flow in a simplified PWR assembly with mixing grid
Keywords: PWR; Mixing grid; Fuel assembly; Turbulence; LES; HPC;
ATWS analysis for Maanshan PWR using TRACE/SNAP code
Keywords: ATWS; Maanshan; PWR; TRACE
Support vector regression model based predictive control of water level of U-tube steam generators
Keywords: GPC; generalized predictive control; GSS; golden section search; MISO; multiple input single output; MPC; model predictive control; PI; proportional and integral; PWR; pressurized water reactor; RBF; radial basis function; RMSE; root mean square error; SD
Reducing axial offset and improving stability in PWRs by using uranium–thorium fuel
Keywords: Thorium; PWR; Axial offset; Xenon oscillations; Stability
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
Modeling RIA benchmark cases with FRAPTRAN and SCANAIR: A comparative exercise
Keywords: CEA; Comisariat à l'Energie Atomique et aux Energies Alternatives; CIEMAT; Centro de Investigaciones Energéticas Medioambientales y Tecnológicas; CSED; critical strain energy density; CSN; Consejo de Seguridad Nuclear; EDF; Electricité De France; EN