| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comprehensive theoretical assessment of potential ‘tramp uranium’ isotopic evolution in BWR reactors
|
Vasiliev, Alexander
|
|
|
144 |
C |
p.
|
artikel
|
| 2 |
A dynamic model of xenon behavior in the Molten Salt Reactor Experiment
|
Price, Terry
|
|
|
144 |
C |
p.
|
artikel
|
| 3 |
A new hexagonal-Z nodal SN method in SARAX code system
|
Wang, Yongping
|
|
|
144 |
C |
p.
|
artikel
|
| 4 |
A three-dimensional PWR-core pin-by-pin analysis code NECP-Bamboo2.0
|
Li, Yunzhao
|
|
|
144 |
C |
p.
|
artikel
|
| 5 |
Code development and analysis of heat pipe cooled passive residual heat removal system of Molten salt reactor
|
Wang, Chenglong
|
|
|
144 |
C |
p.
|
artikel
|
| 6 |
Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system
|
Zhang, Wenwen
|
|
|
144 |
C |
p.
|
artikel
|
| 7 |
Design and exergy evaluation of a novel parabolic trough solar-nuclear combined system
|
Wang, Gang
|
|
|
144 |
C |
p.
|
artikel
|
| 8 |
Design of a two-degree-of-freedom controller for nuclear reactor power control of pressurized water reactor
|
Wan, Jiashuang
|
|
|
144 |
C |
p.
|
artikel
|
| 9 |
Development and application of MOQUICO code to study molten corium-concrete interaction
|
Xu, Zhichun
|
|
|
144 |
C |
p.
|
artikel
|
| 10 |
Development and testing of a coupled SuperMC and SUBCHANFLOW code for LWR simulations
|
Yu, Louhanrong
|
|
|
144 |
C |
p.
|
artikel
|
| 11 |
Development and verification of heat production and radiation damage energy production cross section module in the nuclear data processing code NECP-Atlas
|
Yin, Wen
|
|
|
144 |
C |
p.
|
artikel
|
| 12 |
Development of Core Monitoring System for a Nuclear Power Plant using Artificial Neural Network Technique
|
Saeed, Asim
|
|
|
144 |
C |
p.
|
artikel
|
| 13 |
DFT + U approach on the electronic and thermal properties of hypostoichiometric UO 2
|
Kaloni, T.P.
|
|
|
144 |
C |
p.
|
artikel
|
| 14 |
Disengagement of dispersed cerium oxalate from nitric-oxalic acid medium in a batch settler: Measurements and CFD simulations
|
Panda, Saroj K.
|
|
|
144 |
C |
p.
|
artikel
|
| 15 |
Dynamic sensitivity and uncertainty analysis of a small lead cooled reactor
|
Reale Hernandez, Cuauhtemoc
|
|
|
144 |
C |
p.
|
artikel
|
| 16 |
Editorial Board
|
|
|
|
144 |
C |
p.
|
artikel
|
| 17 |
Effects of newly developed entrainment model for a thermal hydraulic system code (SPACE) based on breakup of large droplets in reflood
|
Yoon, Seung Hyun
|
|
|
144 |
C |
p.
|
artikel
|
| 18 |
Estimation of the likelihood of severe accident management decision-making using a fuzzy logic model
|
Suh, Young A
|
|
|
144 |
C |
p.
|
artikel
|
| 19 |
Experimental and numerical studies on two-phase flow instability behavior of a parallel helically coiled system
|
Wang, Minglu
|
|
|
144 |
C |
p.
|
artikel
|
| 20 |
Extension and validation of aerosol wash-down model on inclined wall
|
Wang, Fangnian
|
|
|
144 |
C |
p.
|
artikel
|
| 21 |
Fission product releases from thoria and urania fuels under reactor accident conditions: Hot cell experiment #6 (HCE6)
|
Dickson, Raymond S.
|
|
|
144 |
C |
p.
|
artikel
|
| 22 |
Improvement and validation of the heat transfer model for the containment module in the RCS-containment integral system code
|
Ge, Li
|
|
|
144 |
C |
p.
|
artikel
|
| 23 |
Improvement of CINDER library for PWR burnup calculations
|
Tavakkoli, Ehsan
|
|
|
144 |
C |
p.
|
artikel
|
| 24 |
Investigation of a fast partial defect detection method for safeguarding PWR spent fuel assemblies
|
Lee, Haneol
|
|
|
144 |
C |
p.
|
artikel
|
| 25 |
Investigation on fluidelastic instability of tube bundles considering the effect of slip ratio of air-water two-phase flow
|
Lai, Jiang
|
|
|
144 |
C |
p.
|
artikel
|
| 26 |
Jeffery David Lewins 1930–2019
|
|
|
|
144 |
C |
p.
|
artikel
|
| 27 |
Multi-physics numerical analysis of the fuel-addition transients in the liquid-fuel molten salt reactor
|
Wan, Chenghui
|
|
|
144 |
C |
p.
|
artikel
|
| 28 |
Numerical analysis of the effect of horizontal distance between a water mist nozzle and ignition source on reduction in heat release rate
|
Lee, Jaiho
|
|
|
144 |
C |
p.
|
artikel
|
| 29 |
Numerical prediction of a single phase Pressurized Thermal Shock scenario for crack assessment in an Reactor Pressure Vessel wall
|
Uitslag-Doolaard, H.J.
|
|
|
144 |
C |
p.
|
artikel
|
| 30 |
Numerical study of natural convection effects on effective thermal conductivity in a pebble bed
|
Bu, Shanshan
|
|
|
144 |
C |
p.
|
artikel
|
| 31 |
Numerical study on fluidelastic instability of tube bundles in two-phase flow considering the effect of tube boundary constraint
|
Lai, Jiang
|
|
|
144 |
C |
p.
|
artikel
|
| 32 |
Numerical study on the effect of dissymmetry heating on flow instability of supercritical water in two parallel channels
|
Liu, Jialun
|
|
|
144 |
C |
p.
|
artikel
|
| 33 |
Numerical study on the uncertainty reduction for thermal power estimation of an open pool research reactor with natural convection core cooling
|
Kim, Hyunjong
|
|
|
144 |
C |
p.
|
artikel
|
| 34 |
On the performance of nanofluids in APR 1400 PLUS7 assembly: Neutronics
|
Khuwaileh, Bassam A.
|
|
|
144 |
C |
p.
|
artikel
|
| 35 |
Optimization of light water reactor High Level Waste disposal scenario in the situation of delayed reprocessing with existing and demonstrated technology
|
Fukaya, Yuji
|
|
|
144 |
C |
p.
|
artikel
|
| 36 |
Point reactor kinetics equations from P1 approximation of the transport equations
|
Espinosa-Paredes, G.
|
|
|
144 |
C |
p.
|
artikel
|
| 37 |
Potential fuel cycle performance of floating small modular light water reactors of Russian origin
|
Hernandez, Richard
|
|
|
144 |
C |
p.
|
artikel
|
| 38 |
Progress in studying the fretting wear/corrosion of nuclear steam generator tubes
|
Guo, Xianglong
|
|
|
144 |
C |
p.
|
artikel
|
| 39 |
Reaction rate analyses of high-energy neutrons by injection of 100 MeV protons onto lead–bismuth target
|
Pyeon, Cheol Ho
|
|
|
144 |
C |
p.
|
artikel
|
| 40 |
Reliability assessment of passive systems using artificial neural network based response surface methodology
|
Solanki, R.B.
|
|
|
144 |
C |
p.
|
artikel
|
| 41 |
Research on level 1 PSA and risk-informed design for ACP100
|
Deng, Jian
|
|
|
144 |
C |
p.
|
artikel
|
| 42 |
Research on the software reliability quantitative evaluation of nuclear power plant digital control system based on non-homogeneous poisson process model
|
Zhang, Qing
|
|
|
144 |
C |
p.
|
artikel
|
| 43 |
Review on sensors to measure control rod position for nuclear reactor
|
Hu, Guang
|
|
|
144 |
C |
p.
|
artikel
|
| 44 |
Review on separation mechanism of corrugated plate separator
|
Chen, Bowen
|
|
|
144 |
C |
p.
|
artikel
|
| 45 |
Safety aspects of spent fuel management in nuclear power plants during transition to decommissioning
|
Liu, Ru-Feng
|
|
|
144 |
C |
p.
|
artikel
|
| 46 |
Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask
|
Alrawash, Saed
|
|
|
144 |
C |
p.
|
artikel
|
| 47 |
Simulation and uncertainty analysis of main steam line break accident on an integral test facility
|
Yang, Ye
|
|
|
144 |
C |
p.
|
artikel
|
| 48 |
Simulation investigation on flashing-induced instabilities in a natural circulation system
|
Zhao, Yanan
|
|
|
144 |
C |
p.
|
artikel
|
| 49 |
Statistical characterization of NPP transients: Application to PWR LBLOCA
|
Fernández-Cosials, Kevin
|
|
|
144 |
C |
p.
|
artikel
|
| 50 |
Study on the soil evaluation methodology of on and offsite Kori Unit 1
|
Byon, Jihyang
|
|
|
144 |
C |
p.
|
artikel
|
| 51 |
Symmetries of the P 3 approximation to the Boltzmann neutron transport equation
|
Pittman, Emily R.
|
|
|
144 |
C |
p.
|
artikel
|
| 52 |
The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs
|
Hombourger, Boris
|
|
|
144 |
C |
p.
|
artikel
|
| 53 |
Three-dimensional numerical study on the effect of sidewall crust thermal resistance on transient MCCI by improved MPS method
|
Cai, Qinghang
|
|
|
144 |
C |
p.
|
artikel
|
| 54 |
Uncertainty & sensitivity analyses for LOCA simulation of PHEBUS experiment FPT-1 using a modified SUNSET code
|
Foad, B.
|
|
|
144 |
C |
p.
|
artikel
|
| 55 |
X2 VVER-1000 benchmark revision: Fresh HZP core state and the reference Monte Carlo solution
|
Bilodid, Yuri
|
|
|
144 |
C |
p.
|
artikel
|
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