Narrowing transient testing pulse widths to enhance LWR RIA experiment design in the TREAT facility
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.10.030
Numerical study of thermal hydraulics behavior on the integral test facility for passive containment cooling system using GASFLOW-MPI
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.09.014
Re-assessment of station blackout accident in VVER-1000 NPP with additional measures following Fukushima accident using Relap/Mod3.2
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.02.006
GPU accelerated lattice Boltzmann method in neutron kinetics problems
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.02.009
Transient analysis of C5G7-TD benchmark with MPACT
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.10.049
Minor Actinides transmutation in candidate accident tolerant fuel-claddings U3Si2-FeCrAl and U3Si2-SiC
来源期刊:Annals of Nuclear EnergyDOI:10.1016/j.anucene.2018.12.003
A leakage correction with SPH factors for two-group constants in GET-based pin-by-pin reactor analyses
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.01.032
Effect of kinetics parameters on transients calculations in external source driven subcritical VR-1 reactor
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.09.007
The thermal hydraulic phenomenon in tight lattice bundles: A review
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.11.037
Stability analysis of the CMFD scheme with linear prolongation
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.02.011
Control rod treatment for FEM based radiation transport methods
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.11.054
Sensitivity methods for effective delayed neutron fraction and neutron generation time with summon
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.11.042
Neutronic analysis of thorium MOX fuel blocks with different driver fuels in advanced block-type HTRs
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.01.049
Phenomena Identification and Ranking Table (PIRT) study for metallic structural materials for advanced High-Temperature reactor
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.08.036
Uncertainty analysis of rod ejection accident in VVER-1000 reactor
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.06.061
Analysis of start-up and long-term operation characteristics of passive residual heat removal system
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.02.033
Neutronics performance analysis on neutron consumption in a Fusion-Fission Hybrid System for tritium breeding
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.10.042
Spatial decomposition of structured grids for nuclear reactor simulations
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.06.054
Study on neutronics of VVER-1200 with accident tolerant fuel cladding
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.10.040
Calculation of the cross and auto power spectral densities for low neutron counting from pulse mode detectors
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.03.032
Overall thermal-hydraulic behavior in an SBO test using HSIT in the ATLAS facility
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.02.050
Wilks’ formula applied to computational tools: A practical discussion and verification
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.05.012
Analysis of the stochastic point reactor using Wiener-Hermite expansion
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.06.022
An experimental study on debris bed formation behavior at bottom-heated boiling condition
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.10.003
The numerical solution of space-dependent neutron kinetics equations in hexagonal-z geometry using backward differentiation formula with adaptive step size
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.01.004
Detached eddy simulation of turbulent and thermal mixing in a T-junction
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.10.006
Natural circulation flow resistance correlations in a rod bundle channel under vertical, inclined and rolling motion conditions
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.02.031
Scaling and integral effect test on transition from depressurization to long-term gravity injection
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.01.034
A quasi-static Monte Carlo algorithm for the simulation of sub-prompt critical transients
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.11.055
A combined immersed body and adaptive mesh method for simulating neutron transport within complex structures
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.05.044
Analytical solution for the Doppler broadening function using the Kaniadakis distribution
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.11.023
Experimental and numerical study on helium flow characteristics in randomly packed pebble bed
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.01.016
Physics characteristics of internally cooled annular fuel for potential application in pressure tube heavy water reactors
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.10.028
Ultrasonic high frequency guided wave for detection and identification of defect location in seal welds of sodium cooled fast reactor fuel subassemblies
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.06.064
Development of the RAINBOW code to evaluate assembly bowing reactivity coefficients in sodium-cooled fast reactors
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.02.004
A robust multi phase model to investigate molten material relocation during total flow blockage in SFR fuel subassembly
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.05.007
A rehomogenization-based approach to model spectral effects of local nuclide density changes in nodal calculations
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.10.061
Establishing safety goals on radiation protection for a space reactor through a case assessment of a loss-of-coolant accident in the International Space Station
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.06.016
Covariance-oriented sample transformation: A new sampling method for reactor-physics uncertainty analysis
来源期刊:Annals of Nuclear EnergyDOI:10.1016/j.anucene.2019.07.001
Fuel management code system against experimental measurements of the CMRR reactor
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.02.038
Boiling water cooled travelling wave reactor
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.06.037
Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.03.023
Analysis and application on sensitivity factors of cross validation of fill rate of CPR1000 unit reactor core coolant monitoring system
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.05.038
An adaptive probabilistic mapping matrix search algorithm for vulnerability analysis of PPS
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.04.013
Core analysis of spectral shift operated SmAHTR
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.09.013
Investigation on the impact of thermal-kernel effect of lithium hydride on the reactivity of nuclear propulsion particle bed reactor
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.12.039
Nth-order multi-response CADIS method to optimize regional variances in a hybrid Monte Carlo simulation
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2018.11.018
Prediction of flow distribution of vertical upward co-current adiabatic annular flow in 8 × 8 rod bundle
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.06.040
An accelerated synchronized forward-adjoint approach in method of characteristics neutron transport solution
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.07.029
Neutronic simulations for the FRM II
来源期刊:Annals of Nuclear EnergyDOI:10.1016/J.ANUCENE.2019.03.010