A review of ground-based robotic systems for the characterization of nuclear environments
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.10.023
Comparison study of photon attenuation characteristics of Poly vinyl alcohol (PVA) doped with Pb(NO3)2 by MCNP5 code, XCOM and experimental results
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.10.018
Estimation of gamma radiation shielding qualification of newly developed glasses by using WinXCOM and MCNPX code
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.029
Enhancement of flame retardancy and radiation shielding properties of ethylene vinyl acetate based radiation shielding composites by EB irradiation
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.01.001
Monte Carlo simulation of Novalis Classic 6 MV accelerator using phase space generation in GATE/Geant4 code
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.004
PWR secondary water chemistry guidelines in Japan - Purpose and technical background
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.01.027
An exploration of the relationship between nuclear decommissioning projects characteristics and cost performance
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.011
A new approach for nuclear reactor analysis based on complex network theory
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.12.008
Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.02.005
Numerical Investigation of Geometric Size Effect on the Internal Heated Water Pool Natural Convection Behavior
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.12.002
A time dependent Monte Carlo approach for nuclear reactor analysis in a 3-D arbitrary geometry
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.024
Global sensitivity analysis of passive safety systems of FHR by using meta-modeling and sampling methods
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.002
Classification of NPPs transients using change of representation technique: A hybrid of unsupervised MSOM and supervised SVM
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103100
Experimental investigation of fluid mixing inside a rod bundle using laser induced fluorescence
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.012
Utilization of harmony search algorithm to optimize a cascade for separating multicomponent mixtures
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.11.005
Precise determination of soil structure parameters in a X-ray and γ-ray CT combination methodology
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.02.007
Modern financial models of nuclear power plants
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.010
Nonlinear analysis of a reduced-order model with relaxation effects for BWRs
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103089
Potential areas for nuclear power plants siting in Saudi Arabia: GIS-based multi-criteria decision making analysis
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.018
Three-dimensional variational nodal method parallelization for pin resolved neutron transport calculations
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.007
A one-dimensional code of the passive residual heat removal system for the modular high temperature gas-cooled reactor
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.10.019
Efficient removal of radioactive iodide anions from simulated wastewater by HDTMA-geopolymer
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103112
Effect of cladding on thermal behavior of nuclear fuel element with non-uniform heat generation
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.10.013
Reliability methods in the design point of free-standing spent fuel racks under seismic conditions
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.021
Impact of integral burnable absorbers on SMART reactor behaviour under normal and anomalous operational conditions
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.005
A CFD-based simulation tool for the stability analysis of natural circulation systems
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103093
Na2Si3O7/BaO composites for the gamma-ray shielding in medical applications: Experimental, MCNP5, and WinXCom studies
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103119
Dissolution behaviour of simulated MOX nuclear fuel pellets in nitric acid medium
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.027
Spatial temperature distribution of fuel assembly pre-simulation for a new simple core degradation experiment
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.11.004
Electronic structures, mechanical properties and defect formation energies of U3Si5 from density functional theory calculations
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.045
A refined time-delay modeling of the molten salt reactor dynamics
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103102
Development and verification of resonance elastic scattering kernel processing module in nuclear data processing code NECP-Atlas
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.10.006
Containment model library of the Apros process simulation software: an overview of development and validation work
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.031
An analytical approach to bifurcations and stability in simplified mathematical models of nuclear reactors
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.008
Fluid-elastic instability evaluation for reactor vessel internals with structural interaction
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.013
GPU-based implementation of a real-time model for atmospheric dispersion of radionuclides
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.015
A method for predicting the structure of corium pool in lower plenum of reactor vessel
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.01.005
Experimental study on performance of helium low pressure compressor of HTR-10GT
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.11.008
Scoping evaluation of trace isotopic ratios within the noble metal-phase as indicators of reactor class
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103059
Assessment of the impact of diversification of uranium switching on the risk of its non-energy use
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.014
Experimental study on the natural circulation capability and heat transfer characteristic of liquid lead bismuth eutectic
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.003
Multiphase flow in small-gap geometry: A combined numerical and experimental study
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.12.010
Non-linear, time dependent target accuracy assessment algorithm for multi-physics, high dimensional nuclear reactor calculations
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.01.023
Non-linear stability analysis of supercritical carbon dioxide flow in inclined heated channel
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103048
Generalized sensitivity analysis of responses to nuclear data in 2-D/1-D transport code KYADJ
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.01.018
End point determination for spent nuclear fuel drying operations
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.04.004
Numerical analysis of dynamic heating modulation during rapid cooling of fuel layer in an indirect-drive cryogenic target
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.02.004
Physics study of liquid hydrogen moderator of CMRR reactor cold neutron source
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.002
Neutronic analysis of a VVER-1000 reactor with nanofluid as coolant through zeroth order average current nodal expansion method
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.016
Laboratory-scale quartz crucible melter tests for vitrifying a high-MoO3 raffinate waste simulant
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.08.022