| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accuracy and efficient solution of helical coiled once-through steam generator model using JFNK method
|
Wu, Yingjie
|
|
|
159 |
C |
p.
|
artikel
|
| 2 |
A data-driven adaptive fault diagnosis methodology for nuclear power systems based on NSGAII-CNN
|
He, Chen
|
|
|
159 |
C |
p.
|
artikel
|
| 3 |
Advanced flow and temperature measurements in a forced convection molten salt test loop
|
Arora, Ojasvin
|
|
|
159 |
C |
p.
|
artikel
|
| 4 |
A multiphysics simulation suite for liquid metal-cooled fast reactors
|
Dawn, William C.
|
|
|
159 |
C |
p.
|
artikel
|
| 5 |
Analysis of ZPPR-15 experimental data for VTR software validation
|
Aliberti, G.
|
|
|
159 |
C |
p.
|
artikel
|
| 6 |
A numerical investigation on the heat transfer and turbulence production characteristics induced by a swirl spacer in a single-tube geometry under single-phase flow condition
|
Abe, Satoshi
|
|
|
159 |
C |
p.
|
artikel
|
| 7 |
A quantification methodology of Seismic Probabilistic Safety Assessment for nuclear power plant
|
Ryu, Junghyun
|
|
|
159 |
C |
p.
|
artikel
|
| 8 |
A review of meta-stable aspects on a subcooled critical flow in nozzles and orifices
|
Kim, Yeon-Sik
|
|
|
159 |
C |
p.
|
artikel
|
| 9 |
Assessment of tritium effluent from Prototype Generation IV Sodium-cooled Fast Reactor
|
Kim, Taek K.
|
|
|
159 |
C |
p.
|
artikel
|
| 10 |
Assessment of WWER 1000 core degradation in a severe accident condition induced by MB-LOCA
|
Groudev, Pavlin
|
|
|
159 |
C |
p.
|
artikel
|
| 11 |
CFD modeling of liquid entrainment through vertical T-junction of fourth stage automatic depressurization system (ADS-4)
|
Khan, Irfan
|
|
|
159 |
C |
p.
|
artikel
|
| 12 |
Clearance of building of a former uranium concentrates plant
|
Vico, A.M.
|
|
|
159 |
C |
p.
|
artikel
|
| 13 |
Compact inertial electrostatic confinement D-D fusion neutron generator
|
Kumar Sharma, Surender
|
|
|
159 |
C |
p.
|
artikel
|
| 14 |
Corrigendum to “Non-intrusive stochastic approach for nuclear cross-sections adjustment” [Ann. Nucl. Energy 155 (2021) 108162]
|
Huang, Dongli
|
|
|
159 |
C |
p.
|
artikel
|
| 15 |
Demonstration of a coupled computational fluid dynamics approach for modelling non-water cooled small modular reactors
|
Podila, K.
|
|
|
159 |
C |
p.
|
artikel
|
| 16 |
Development and application of marginal likelihood optimization for integral parameter adjustment
|
Siefman, Daniel
|
|
|
159 |
C |
p.
|
artikel
|
| 17 |
Development and preliminary verification of a Monte Carlo photon transport code IMPC-Photon
|
Gao, Qingyu
|
|
|
159 |
C |
p.
|
artikel
|
| 18 |
Development and validation of ISOBURN, a new depletion code
|
Tavakkoli, Ehsan
|
|
|
159 |
C |
p.
|
artikel
|
| 19 |
Development of a small modular boiling water reactor combined with external superheaters
|
Wibisono, Andhika Feri
|
|
|
159 |
C |
p.
|
artikel
|
| 20 |
3DGShield: A new 3D gamma ray shielding code for arbitrary source and shield geometry based on point kernel technique
|
Hansda, Manoj Kumar
|
|
|
159 |
C |
p.
|
artikel
|
| 21 |
Dynamic simulation of the gas-cooled space nuclear reactor system using SIMCODE
|
Meng, Tao
|
|
|
159 |
C |
p.
|
artikel
|
| 22 |
Editorial Board
|
|
|
|
159 |
C |
p.
|
artikel
|
| 23 |
Efficiency calibration of LaBr3(Ce) and NaI(Tl) scintillation detectors with MCNP6 for various in-situ measurements for NPP decommissioning purposes
|
Bednár, Dávid
|
|
|
159 |
C |
p.
|
artikel
|
| 24 |
Evaluation of an improved method and software tool for confirming compliance with release criteria for nuclear facilities
|
Rudas, Csilla
|
|
|
159 |
C |
p.
|
artikel
|
| 25 |
Experimental and numerical study on the critical working condition of control rod in liquid-suspended shutdown device
|
Yang, Zhendong
|
|
|
159 |
C |
p.
|
artikel
|
| 26 |
First demonstration experiment of the neutron rotation method for detecting nuclear material
|
Komeda, M.
|
|
|
159 |
C |
p.
|
artikel
|
| 27 |
Generation method and verification of pebble type VHTR multigroup cross sections based on OpenMC
|
Wang, Jincheng
|
|
|
159 |
C |
p.
|
artikel
|
| 28 |
Integrated analysis of VVER-1000 fuel assembly fueled with accident tolerant fuel (ATF) materials
|
Mohsen, Mohamed Y.M.
|
|
|
159 |
C |
p.
|
artikel
|
| 29 |
Investigation of the efficiency optimization for the improved subgroup resonance self-shielding treatment on the GPU platform
|
Li, Song
|
|
|
159 |
C |
p.
|
artikel
|
| 30 |
Large eddy simulation on the mixing characteristics of liquid sodium at the core outlet of sodium cooled fast reactors (SFR)
|
Wang, Yingjie
|
|
|
159 |
C |
p.
|
artikel
|
| 31 |
Measurements of effective actinides neutron capture cross sections in a cadmium-filtered epithermal neutron spectrum
|
Youinou, G.J.
|
|
|
159 |
C |
p.
|
artikel
|
| 32 |
Modal and structural analysis on a main feed water regulating valve under different loading conditions
|
Wu, Jia-yi
|
|
|
159 |
C |
p.
|
artikel
|
| 33 |
Model based security verification of Cyber-Physical System based on Petrinet: A case study of Nuclear power plant
|
Tripathi, Dipty
|
|
|
159 |
C |
p.
|
artikel
|
| 34 |
Monte-Carlo interpretation of the JANUS Phase 1, Phase 2 and Phase 4 shielding experiments with TRIPOLI-4®
|
Hajji, Amine
|
|
|
159 |
C |
p.
|
artikel
|
| 35 |
Neutron noise simulator based on the boundary element method (BEM)
|
Hosseini, Seyed Abolfazl
|
|
|
159 |
C |
p.
|
artikel
|
| 36 |
Neutrons probability distribution of the coupled reactors kinetics system via Magnus expansion
|
Aboanber, Ahmed E.
|
|
|
159 |
C |
p.
|
artikel
|
| 37 |
Pellet-cladding mechanical interaction analysis of heavy water fuel rods under power ramps
|
Saad, Djillali
|
|
|
159 |
C |
p.
|
artikel
|
| 38 |
Preliminary numerical investigation of TRISO-matrix interface debonding characteristics in fully ceramic microencapsulated fuel
|
Zhang, Cheng
|
|
|
159 |
C |
p.
|
artikel
|
| 39 |
Preliminary uncertainty and sensitivity analysis of the Molten Salt Fast Reactor steady-state using a Polynomial Chaos Expansion method
|
Santanoceto, Mario
|
|
|
159 |
C |
p.
|
artikel
|
| 40 |
PWR core loading pattern optimization with adaptive genetic algorithm
|
So, Chol
|
|
|
159 |
C |
p.
|
artikel
|
| 41 |
Review of interdisciplinary heat transfer enhancement technology for nuclear reactor
|
Lu, Qi
|
|
|
159 |
C |
p.
|
artikel
|
| 42 |
Scaling analysis for single-phase natural circulation under dynamic motion and its verification using MARS-KS code
|
Kim, Geon-Woo
|
|
|
159 |
C |
p.
|
artikel
|
| 43 |
Sensor position optimization for flux mapping in a nuclear reactor using compressed sensing
|
Bahuguna, S.K.
|
|
|
159 |
C |
p.
|
artikel
|
| 44 |
SINBAD – Radiation shielding benchmark experiments
|
Kodeli, Ivan A.
|
|
|
159 |
C |
p.
|
artikel
|
| 45 |
Temperature perturbation method using on-the-fly treatment of the cross-sections in the resolved resonance region
|
Li, Hao
|
|
|
159 |
C |
p.
|
artikel
|
| 46 |
The numerical simulation and analysis of turbulent flow behavior in 5 × 5 fuel rod bundle with split-type mixing vane
|
Wei, Hongyang
|
|
|
159 |
C |
p.
|
artikel
|
| 47 |
Theoretical basis for reduction of number of survey units of MARSSIM final status survey at decommissioning facilities
|
Sohn, Wook
|
|
|
159 |
C |
p.
|
artikel
|
| 48 |
Which nuclear data can be validated with LLNL pulsed-sphere experiments?
|
Neudecker, Denise
|
|
|
159 |
C |
p.
|
artikel
|
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