| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Adaptive filtering based sodium flow measurement method for in-situ calibration
|
Wu, Wen-Kai
|
|
|
150 |
C |
p.
|
artikel
|
| 2 |
Analysis on CHF deviation caused by geometry of the heater blocks in a validation test of IVR-ERVC technology
|
Lu, Daogang
|
|
|
150 |
C |
p.
|
artikel
|
| 3 |
An analysis on the steam generator tube rupture events with core damage
|
Song, JinHo
|
|
|
150 |
C |
p.
|
artikel
|
| 4 |
An assembly-level neutronic calculation method based on LightGBM algorithm
|
Cai, Jiejin
|
|
|
150 |
C |
p.
|
artikel
|
| 5 |
A new correlation for the prediction of critical quality in tubes
|
Wu, Wanze
|
|
|
150 |
C |
p.
|
artikel
|
| 6 |
A spectral nodal method for the adjoint S N neutral particle transport equations in X , Y -geometry: Application to direct and inverse multigroup source-detector problems
|
Curbelo, Jesús P.
|
|
|
150 |
C |
p.
|
artikel
|
| 7 |
A study on the numerical analysis for OFI in a narrow rectangular flow channel
|
Park, Jong-Pil
|
|
|
150 |
C |
p.
|
artikel
|
| 8 |
Axial power distribution control in fast nuclear reactor based on proportional spatial-derivative method
|
Yang, Minghan
|
|
|
150 |
C |
p.
|
artikel
|
| 9 |
CFD analysis on flow and heat transfer characteristic in natural circulation system with subchannels under rolling conditions
|
Wang, Sipeng
|
|
|
150 |
C |
p.
|
artikel
|
| 10 |
Cold spray technology in nuclear energy applications: A review of recent advances
|
Yeom, Hwasung
|
|
|
150 |
C |
p.
|
artikel
|
| 11 |
Design research for the porous hexagonal prism shaped fuel element adopted in nuclear thermal propulsion reactor based on neutronics and thermal-hydraulics coupled method
|
Zhang, Jun
|
|
|
150 |
C |
p.
|
artikel
|
| 12 |
Detection of subassembly bowing in a fast breeder reactor using glancing angle ultrasonic imaging
|
Chaitanya, G.M.S.K.
|
|
|
150 |
C |
p.
|
artikel
|
| 13 |
Development and assessment of a nearly autonomous management and control system for advanced reactors
|
Lin, Linyu
|
|
|
150 |
C |
p.
|
artikel
|
| 14 |
Development and verification of a simulation toolkit for Self-Powered Neutron Detector
|
Sang, Yaodong
|
|
|
150 |
C |
p.
|
artikel
|
| 15 |
Development of canisters for spent fuels of VVER-1200 and ATMEA1 new generation reactors and determination of geological disposal densities
|
Özeşme, Gürel
|
|
|
150 |
C |
p.
|
artikel
|
| 16 |
Development of in-core fuel management tool for AHWR using artificial neural networks
|
Thakur, Amit
|
|
|
150 |
C |
p.
|
artikel
|
| 17 |
Editorial Board
|
|
|
|
150 |
C |
p.
|
artikel
|
| 18 |
Experimental investigation on the transient film boiling heat transfer during quenching of FeCrAl
|
Wang, Zefeng
|
|
|
150 |
C |
p.
|
artikel
|
| 19 |
Fault identification and diagnosis based on KPCA and similarity clustering for nuclear power plants
|
Wang, Hang
|
|
|
150 |
C |
p.
|
artikel
|
| 20 |
Global error analysis of the Chebyshev rational approximation method
|
Calvin, Olin
|
|
|
150 |
C |
p.
|
artikel
|
| 21 |
Global sensitivity analysis of the main steam line break accident by using sampling methods and surrogate models
|
Sun, Qiuteng
|
|
|
150 |
C |
p.
|
artikel
|
| 22 |
GOTHIC simulations of OECD/NEA THAI multi-vessel hydrogen deflagration tests
|
Lebel, Luke
|
|
|
150 |
C |
p.
|
artikel
|
| 23 |
Hydraulic design of an advanced second shutdown system for a research reactor
|
Kim, In Guk
|
|
|
150 |
C |
p.
|
artikel
|
| 24 |
Immobilization of iodine waste forms: A low-sintering temperature with Bi2O3-B2O3-ZnO glass
|
Wei, Guilin
|
|
|
150 |
C |
p.
|
artikel
|
| 25 |
Improvements of turbulence model for analysis of hydrogen stratification erosion by turbulent buoyant jet
|
Tong, Lili
|
|
|
150 |
C |
p.
|
artikel
|
| 26 |
Lattice physics calculations using the embedded self-shielding method in polaris, Part II: Benchmark assessment
|
Mertyurek, Ugur
|
|
|
150 |
C |
p.
|
artikel
|
| 27 |
Lattice physics calculations using the embedded self-shielding method in Polaris, Part I: Methods and implementation
|
Jessee, Matthew A.
|
|
|
150 |
C |
p.
|
artikel
|
| 28 |
Low power transient analysis of PWR reload core with fixed neutron source via 3-D nodal diffusion code RAST-K
|
Jo, YuGwon
|
|
|
150 |
C |
p.
|
artikel
|
| 29 |
Maintenance strategy design for nuclear reactors safety systems using a constraint particle swarm evolutionary methodology
|
Wang, Jinkai
|
|
|
150 |
C |
p.
|
artikel
|
| 30 |
Measurement of tungsten granular target worth on VENUS-II light water reactor and validation of the granular target model
|
Gu, Long
|
|
|
150 |
C |
p.
|
artikel
|
| 31 |
Methods and results of determining the impurity gas amount in ceramic fuel
|
Vityuk, Galina
|
|
|
150 |
C |
p.
|
artikel
|
| 32 |
Neutronics analysis of the stellarator-type fusion-fission hybrid reactor based on the CAD optimization method
|
Li, Jin-Yang
|
|
|
150 |
C |
p.
|
artikel
|
| 33 |
Numerical simulation of CS28-1 experiment by using CANDU severe accident analysis code, CAISER
|
Bae, Jun Ho
|
|
|
150 |
C |
p.
|
artikel
|
| 34 |
Numerical simulation of heat transfer behavior in EAGLE ID1 in-pile test using finite volume particle method
|
Zhang, Ting
|
|
|
150 |
C |
p.
|
artikel
|
| 35 |
Numerical simulations of the Rayleigh-Bénard-Marangoni convections in a thin metallic layer
|
Dang, Chunhui
|
|
|
150 |
C |
p.
|
artikel
|
| 36 |
Passive gamma emission tomography with ordered subset expectation maximization method
|
Shiba, Shigeki
|
|
|
150 |
C |
p.
|
artikel
|
| 37 |
Performance analysis of a multi-stage safety injection tank
|
Shin, Soo Jai
|
|
|
150 |
C |
p.
|
artikel
|
| 38 |
Pilot-scale removal of uranium from uranium plant wastewater using industrial iron powder in the ultrasonic field
|
Liao, Tianqi
|
|
|
150 |
C |
p.
|
artikel
|
| 39 |
Py-MLBUF: Development of an online-platform for gamma-ray shielding calculations and investigations
|
Mann, Kulwinder Singh
|
|
|
150 |
C |
p.
|
artikel
|
| 40 |
Recent progress of CFD applications in PWR thermal hydraulics study and future directions
|
Wang, Mingjun
|
|
|
150 |
C |
p.
|
artikel
|
| 41 |
Research on the flywheel clearance flow in canned motor RCP
|
Xu, Rui
|
|
|
150 |
C |
p.
|
artikel
|
| 42 |
Results of the AGR-2 TRISO fuel performance demonstration irradiation experiment in the Advanced Test Reactor
|
Demkowicz, Paul A.
|
|
|
150 |
C |
p.
|
artikel
|
| 43 |
Rod bundle thermal-hydraulics experiment with water and water- Al 2 O 3 nanofluid for small modular reactor
|
Bhowmik, Palash K.
|
|
|
150 |
C |
p.
|
artikel
|
| 44 |
Seismic response correlation coefficient for the structures, systems and components of the Korean nuclear power plant for seismic probabilistic safety assessment
|
Eem, Seunghyun
|
|
|
150 |
C |
p.
|
artikel
|
| 45 |
Sensitivity analysis of core slumping and debris quenching behavior of Fukushima Daiichi Unit-3 accident
|
Li, Xin
|
|
|
150 |
C |
p.
|
artikel
|
| 46 |
SMART with trans-critical CO2 power conversion system for maritime propulsion in Northern Sea Route, part 2: Transient analysis
|
Oh, Bong Seong
|
|
|
150 |
C |
p.
|
artikel
|
| 47 |
Statistical method for determining the onset of nucleate boiling under forced and natural convections in a rectangular channel
|
Park, Ji-Hwan
|
|
|
150 |
C |
p.
|
artikel
|
| 48 |
Three-dimensional modeling and loss-of-coolant accident analysis of high temperature gas cooled reactor
|
Zhang, Shuangbao
|
|
|
150 |
C |
p.
|
artikel
|
| 49 |
Two-sensor droplet-capable conductivity probe for measurement in liquid dispersed flows
|
Zhu, Qingzi
|
|
|
150 |
C |
p.
|
artikel
|
| 50 |
Uncertainty quantification analysis and statistical estimation for LBLOCA in a PWR using Monte-Carlo and alternative methods
|
Kang, Dong Gu
|
|
|
150 |
C |
p.
|
artikel
|
| 51 |
Verification of on-the-fly homogenization method based on the analysis of HTTR
|
Yuan, Yuan
|
|
|
150 |
C |
p.
|
artikel
|
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