| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A geometry conforming isogeometric method for the self-adjoint angular flux (SAAF) form of the neutron transport equation with a discrete ordinate ( S N ) angular discretisation
|
Latimer, C.
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 2 |
Analysis of single failure criteria and operator action effect for different SGTR mitigation strategies of HPR1000
|
Sui, Danting
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 3 |
Analysis of special phenomena of droplet impact on horizontal liquid film at low velocity
|
Chen, Bowen
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 4 |
Application of adjoint based node optimization method to nuclear thermal-hydraulic system analysis code
|
Lee, Jae Jun
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 5 |
Application of the hyperfine group self-shielding calculation method to the lattice and whole-core physics calculation
|
Zu, Tiejun
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 6 |
Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT)
|
Williams, W.J.
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 7 |
Benchmark experiments with slab sample using time-of-flight technique at CIAE
|
Nie, Yangbo
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 8 |
Boric acid and boiling time effects on critical heat flux for corrosive and non-corrosive materials
|
Kam, Dong Hoon
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 9 |
Compression of 3D pin-by-pin burnup data
|
Tomatis, Daniele
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 10 |
Computational effort comparison of genetic algorithm and particle swarm optimization algorithms for the proportional–integral–derivative controller tuning of a pressurized water nuclear reactor
|
Mousakazemi, Seyed Mohammad Hossein
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 11 |
Critical flow prediction using simplified cascade fuzzy neural networks
|
An, Ye Ji
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 12 |
Design improvements to the ISU AGN-201 reactor SCRAM, interlock, and magnet circuits
|
Mallicoat, Adam
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 13 |
Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
|
Kim, Wonkyeong
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 14 |
Development of a robust multi-phase heat transfer model and optimization of multi-layer core catcher for future Indian sodium cooled fast reactors
|
Bala Sundaram, G.
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 15 |
Dynamic characteristics analysis of the hydro-hybrid liquid Sodium lubricated bearing-rotor coupled system in the two-circuit main loop liquid sodium pump system
|
Xie, Zhongliang
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 16 |
Editorial Board
|
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 17 |
Effects of oxidation and secondary hydriding during simulated loss-of-coolant-accident tests on the bending strength of Zircaloy-4 fuel cladding tube
|
Okada, Yuji
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 18 |
Estimation of neutron sources driving prescribed power generations in subcritical systems using one-speed two-dimensional discrete ordinates formulations
|
Moraes, Leonardo R.C.
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 19 |
Evaluation of cancer risk after a release from a hypothetical nuclear reactor steam generator tube rupture accident (SGTR)
|
Andrade, Edson R.
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 20 |
Evaluation of thermal stability in deep geological repository and nuclear criticality safety of spent nuclear fuel vitrified in iron phosphate glass
|
Won Lee, Cheong
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 21 |
Experimental and analytical study on heat dissipation mechanisms during spent fuel unloading in sodium fast reactor
|
Xiong, Jinbiao
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 22 |
Experimental investigation of steam-air condensation on containment vessel
|
Chen, Ronghua
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 23 |
Experimental study of raining effect on the inner surface of containment roof
|
Tan, Bing
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 24 |
Experimental study on startup performance of high temperature potassium heat pipe at different inclination angles and input powers for nuclear reactor application
|
Wang, Chenglong
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 25 |
Experimental study on the novel rolling-sliding integrated auxiliary bearing in active magnetic bearing during rotor drop
|
Liu, Xingnan
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 26 |
Experimental study on transient characteristics of reactor coolant pump under rotor seizure accident
|
Wang, Xiuli
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 27 |
IFDF acceleration method with adaptive diffusion coefficients for SN nodal calculation in SARAX code system
|
Xu, Zhitao
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 28 |
Implementation of burnup effects in the multiphysics fuel behavior module FINIX
|
Loukusa, Henri
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 29 |
Improvements of subgroup method based on fine group slowing-down calculation for resonance self-shielding treatment
|
Li, Song
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 30 |
Improvements on the method of ultra-fine-group slowing-down solution coupled with method of characteristics on irregular geometries
|
Zhang, Qian
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 31 |
Investigations of the fresh-core cycle-length and the average fuel depletion analysis of the NuScale core
|
Sadegh-Noedoost, A.
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 32 |
Local effect model development for the steam generator three dimensional thermal hydraulics analysis code
|
Wang, Xi
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 33 |
Modeling of PANDA isolation condenser experiments with MELCOR and Apros
|
Sevón, Tuomo
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 34 |
Modelling of a Nordic BWR containment and suppression pool behavior during a LOCA with GOTHIC 8.1
|
Estévez-Albuja, Samanta
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 35 |
Multiphysics modeling of thorium-based fuel performance with a two-layer SiC cladding in a light water reactor
|
Liu, Rong
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 36 |
Neutronic analysis of thorium S&B fuel blocks with different driver fuels in advanced Block-type HTRs
|
Mutwakkil Attom, Areej
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 37 |
Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculation
|
Du, Xianan
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 38 |
Nuclear accident source term estimation using Kernel Principal Component Analysis, Particle Swarm Optimization, and Backpropagation Neural Networks
|
Ling, Yongsheng
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 39 |
Numerical analysis of how ventilation conditions impact compartment fire suppression by water mist
|
Lee, Jaiho
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 40 |
Numerical assessment of packed-bed heat transfer correlations for molten salt
|
Dave, A.J.
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 41 |
On the scaling of uncertainties in thermal hydraulic system codes
|
Casamor, M.
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 42 |
Seismic stability reliability assessment of nuclear power plant’s bank revetment considering unreinforced and reinforced situations
|
Xu, Bin
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 43 |
Static and dynamic reliability studies of a fast reactor shutdown system using smart component method
|
Shukla, Darpan Krishnakumar
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 44 |
Stochastic mixing of bound thermal scattering data in MONK
|
Richards, Simon
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 45 |
Study of the influence of water gaps between fuel assemblies on the activation of an aeroball measurement system (AMS)
|
Konheiser, J.
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 46 |
Study on fracture morphology of water film on the wall of vertical corrugated plate under shear of the air flow
|
Wang, Bo
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 47 |
The correlation matrix for the effective delayed neutron parameters of the IPEN/MB-01 reactor
|
dos Santos, Adimir
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 48 |
The investigation and calculation of the transmutation paths for the production of 252cf in fast reactors
|
Wu, Mingyu
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 49 |
The measure on mitigating hydrogen risk during LOCA accident in nuclear power plant
|
Meng, Xiangyuan
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 50 |
Thermal-hydraulic analysis of the thermoelectric space reactor power system with a potassium heat pipe radiator
|
Zhang, Wenwen
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 51 |
Time-dependent integral transport in one-dimensional infinite media using dimensionless variables and the reduced collision formulation
|
Moll, E.C.
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 52 |
Time-frequency analysis of non-stationary neutron noise in a small modular nuclear reactor
|
Tayefi, Shima
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 53 |
Use of GPT for stabilization and acceleration of search mechanisms in industrial core computations
|
van Geemert, René
|
|
2020
|
136 |
C |
p.
|
artikel
|
| 54 |
Validation of CASMO5 neutron kinetics parameters
|
Hykes, Joshua M.
|
|
2020
|
136 |
C |
p.
|
artikel
|
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