| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Acceleration of the exponential function expansion nodal SP3 method by multi-group GMRES algorithm for PWR pin-by-pin calculation
|
Yang, Wen
|
|
2018
|
120 |
C |
p. 869-879
|
artikel
|
| 2 |
Accurate resonance absorption calculation for fuel pins with non-uniform intra-pellet temperature profile based on ultra-fine-group slowing-down calculations
|
Zhang, Qian
|
|
2018
|
120 |
C |
p. 392-401
|
artikel
|
| 3 |
Accurate resonance calculation method coupling simplified embedded self-shielding method and ultra-fine group method
|
Zu, Tiejun
|
|
2018
|
120 |
C |
p. 198-206
|
artikel
|
| 4 |
Adaptive mesh method applied to the thermal hydraulic program of system code with a judging criterion based on the matrix error
|
Zhao, Xiumei
|
|
2018
|
120 |
C |
p. 723-734
|
artikel
|
| 5 |
Advanced combinatorial method for solving complex fault trees
|
Rivero Oliva, José de Jesús
|
|
2018
|
120 |
C |
p. 666-681
|
artikel
|
| 6 |
Analysis of minor actinide recycling using MOX fuel assemblies in a Boiling Water Reactor
|
Alonso, Gustavo
|
|
2018
|
120 |
C |
p. 8-26
|
artikel
|
| 7 |
A new experimental investigation on local fuel-coolant interaction in a molten pool
|
Zhang, Ting
|
|
2018
|
120 |
C |
p. 593-603
|
artikel
|
| 8 |
A new organization-oriented technique of human error analysis in digital NPPs: Model and classification framework
|
Li, Peng-cheng
|
|
2018
|
120 |
C |
p. 48-61
|
artikel
|
| 9 |
A new propagation analysis of statistical uncertainty in multi-group cross sections generated by Monte Carlo method
|
Lee, Jae Yong
|
|
2018
|
120 |
C |
p. 477-484
|
artikel
|
| 10 |
Artificial neural network algorithms for pulse shape discrimination and recovery of piled-up pulses in organic scintillators
|
Fu, C.
|
|
2018
|
120 |
C |
p. 410-421
|
artikel
|
| 11 |
A simulator based on virtual reality to dismantle a research reactor assembly using master-slave manipulators
|
Nash, B.
|
|
2018
|
120 |
C |
p. 1-7
|
artikel
|
| 12 |
A study on reliability assessment of a decay heat removal system for a sodium-cooled fast reactor
|
Kim, Jintae
|
|
2018
|
120 |
C |
p. 534-539
|
artikel
|
| 13 |
A stylized 3D Advanced High Temperature Reactor (AHTR) benchmark problem
|
Zhang, Dingkang
|
|
2018
|
120 |
C |
p. 178-185
|
artikel
|
| 14 |
A transient CFD research on the dynamic characteristics of liquid annular seals
|
Xu, Rui
|
|
2018
|
120 |
C |
p. 528-533
|
artikel
|
| 15 |
Burnup performance of MOX and Pu-ROX fuels in small pebble bed reactor with accumulative fuel loading scheme
|
Simanullang, Irwan Liapto
|
|
2018
|
120 |
C |
p. 450-460
|
artikel
|
| 16 |
Capabilities of high y+ wall approaches in predicting heat transfer to supercritical fluids in rod bundle geometries
|
Brogna, Chiara
|
|
2018
|
120 |
C |
p. 272-278
|
artikel
|
| 17 |
Carburization effects on the corrosion of Cr, Fe, Ni, W, and Mo in fluoride-salt cooled high temperature reactor (FHR) coolant
|
Chan, Kevin J.
|
|
2018
|
120 |
C |
p. 279-285
|
artikel
|
| 18 |
Comparisons between RFSP and MCNP for modeling pressure tube heavy water reactor cores with thorium-based fuels
|
Yan, Huiping
|
|
2018
|
120 |
C |
p. 642-655
|
artikel
|
| 19 |
Control rod position measurement with helix-electrode capacitance sensor in nuclear heating reactor
|
Hu, Guang
|
|
2018
|
120 |
C |
p. 788-797
|
artikel
|
| 20 |
Core optimization of 5 MWth Lead-bismuth cooled Super small Module Reactor (LSMR) based on separative work
|
Chen, Zhong
|
|
2018
|
120 |
C |
p. 735-741
|
artikel
|
| 21 |
Corrigendum to “Thermal neutron albedo measurements for multilithic reflectors” [Ann. Nucl. Energy, 62 (2013) 1–7]
|
Mehboob, Khurram
|
|
2018
|
120 |
C |
p. 569
|
artikel
|
| 22 |
Dependability analysis of safety critical systems: Issues and challenges
|
Kaur, Raj kamal
|
|
2018
|
120 |
C |
p. 127-154
|
artikel
|
| 23 |
Design evaluation of large-scale sodium integral effect test facility (STELLA-2) using MARS-LMR
|
Lee, Jewhan
|
|
2018
|
120 |
C |
p. 845-856
|
artikel
|
| 24 |
Design strategies for LWR and VHTR test environments in a fast spectrum reactor
|
Scherr, Jonathan
|
|
2018
|
120 |
C |
p. 219-235
|
artikel
|
| 25 |
Determination of prompt neutron decay constant by time-domain fluctuation analyses of detector current signals
|
Kitamura, Yasunori
|
|
2018
|
120 |
C |
p. 691-706
|
artikel
|
| 26 |
Development of a Bayesian belief network model for software reliability quantification of digital protection systems in nuclear power plants
|
Kang, Hyun Gook
|
|
2018
|
120 |
C |
p. 62-73
|
artikel
|
| 27 |
Editorial Board
|
|
|
2018
|
120 |
C |
p. ii
|
artikel
|
| 28 |
Effects of ballooning and rupture on the fracture resistance of Zircaloy-4 fuel cladding tube after LOCA-simulated experiments
|
Yumura, Takanori
|
|
2018
|
120 |
C |
p. 798-804
|
artikel
|
| 29 |
Effects of low-Re pulsatile flow on friction characteristics in bare square array rod bundles
|
Ala, Ayodeji Adebisi
|
|
2018
|
120 |
C |
p. 630-641
|
artikel
|
| 30 |
Electrochemical behavior of dysprosium and lanthanum in molten LiF-NaF-KF (Flinak) salt
|
Chesser, Ryan
|
|
2018
|
120 |
C |
p. 246-252
|
artikel
|
| 31 |
Essentially nonnegative matrix exponential methods for nuclide transmutation
|
Müller, Erwin
|
|
2018
|
120 |
C |
p. 611-624
|
artikel
|
| 32 |
Estimation of resonance self-shielding effect in PWR pin cell for different fuel types
|
Foad, Basma
|
|
2018
|
120 |
C |
p. 805-813
|
artikel
|
| 33 |
Experimental and numerical investigation of molten corium behavior in lower head under external subcooling and boiling conditions
|
Pandazis, P.
|
|
2018
|
120 |
C |
p. 888-895
|
artikel
|
| 34 |
Fast solution of neutron transport SP3 equation by reduced basis finite element method
|
Zhang, Chunyu
|
|
2018
|
120 |
C |
p. 707-714
|
artikel
|
| 35 |
Fission chambers for space effect reduction in the application of the area method
|
Janczyszyn, Jerzy
|
|
2018
|
120 |
C |
p. 896-898
|
artikel
|
| 36 |
Flow and heat transfer behaviors for double-walled-straight-tube heat exchanger of HLM loop
|
Liu, Shuyong
|
|
2018
|
120 |
C |
p. 604-610
|
artikel
|
| 37 |
Flow characteristics inside a single basket containing a nuclear fuel assembly
|
Yu, Seung-Hwan
|
|
2018
|
120 |
C |
p. 715-722
|
artikel
|
| 38 |
Flow pattern effect on two-phase pressure drops in vertical upward flow across a horizontal tube bundle
|
Zhang, K.
|
|
2018
|
120 |
C |
p. 253-264
|
artikel
|
| 39 |
Flow visualization study of flow-induced acoustic resonance in closed side branches
|
Xiao, Yao
|
|
2018
|
120 |
C |
p. 559-568
|
artikel
|
| 40 |
Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings
|
Wagih, Malik
|
|
2018
|
120 |
C |
p. 304-318
|
artikel
|
| 41 |
High-energy nuclear data uncertainties propagated to MYRRHA safety parameters
|
Stankovskiy, Alexey
|
|
2018
|
120 |
C |
p. 207-218
|
artikel
|
| 42 |
History review of nuclear reactor safety
|
Gu, Zhixing
|
|
2018
|
120 |
C |
p. 682-690
|
artikel
|
| 43 |
Improvement of the MARS subcooled boiling model for low-pressure, low-Pe flow conditions
|
Ha, Tae Wook
|
|
2018
|
120 |
C |
p. 236-245
|
artikel
|
| 44 |
Initial core design of CANDLE burning fast reactor using plutonium from LWR spent fuel
|
Osato, Hiroki
|
|
2018
|
120 |
C |
p. 501-508
|
artikel
|
| 45 |
Inline critical boron concentration search with p-CMFD feedback in whole-core continuous-energy Monte Carlo simulation
|
Jo, YuGwon
|
|
2018
|
120 |
C |
p. 402-409
|
artikel
|
| 46 |
Investigation on the heterogeneous resonance integral in the embedded self-shielding method
|
Zhang, Qian
|
|
2018
|
120 |
C |
p. 485-500
|
artikel
|
| 47 |
Mechanism analysis of the contribution of nuclear data to the k eff uncertainty in the pebble bed HTR
|
Hao, Chen
|
|
2018
|
120 |
C |
p. 857-868
|
artikel
|
| 48 |
Mesh-free RBF collocation method to solve the multi-group SN neutron transport equation in arbitrary domains
|
Kashi, S.
|
|
2018
|
120 |
C |
p. 118-126
|
artikel
|
| 49 |
Metaheuristic optimization in shielding design for neutrons and gamma rays reducing dose equivalent as much as possible
|
Cai, Yao
|
|
2018
|
120 |
C |
p. 27-34
|
artikel
|
| 50 |
Mitigation of source term in suppression pools: Large uncertainties in predictability
|
Herranz, L.E.
|
|
2018
|
120 |
C |
p. 509-515
|
artikel
|
| 51 |
Modeling and mitigation of bundle end power peaking in pressure tube heavy water reactor advanced fuels using thorium dioxide
|
Dugal, C.
|
|
2018
|
120 |
C |
p. 625-629
|
artikel
|
| 52 |
Neutronic experiments with fluorine rich compounds at LR-0 reactor
|
Losa, E.
|
|
2018
|
120 |
C |
p. 286-295
|
artikel
|
| 53 |
Neutronics analysis of CNPP-II loaded with 1/3rd MOX fuel
|
Gul, Anas
|
|
2018
|
120 |
C |
p. 839-844
|
artikel
|
| 54 |
New kinetic simulation capabilities for Tripoli-4®: Methods and applications
|
Faucher, Margaux
|
|
2018
|
120 |
C |
p. 74-88
|
artikel
|
| 55 |
NPP main feedwater flow Venturi tube erosion characteristics study and improvement
|
Yongwei, Chen
|
|
2018
|
120 |
C |
p. 828-834
|
artikel
|
| 56 |
Nuclear data sensitivity for reactor physics parameters in a lead-cooled reactor
|
Trottier, Alexandre
|
|
2018
|
120 |
C |
p. 333-347
|
artikel
|
| 57 |
Nuclear safety-critical Digital Instrumentation and Control system software: Reliability demonstration
|
Guo, Jia
|
|
2018
|
120 |
C |
p. 516-527
|
artikel
|
| 58 |
Numerical investigations on the coupling of the one-group interfacial area transport equation and subcooled boiling models for nuclear safety applications
|
Alali, Abdullah
|
|
2018
|
120 |
C |
p. 155-168
|
artikel
|
| 59 |
Numerical simulation of wall condensation and direct contact condensation in containment suppression pool of PWR
|
Li, Jingya
|
|
2018
|
120 |
C |
p. 108-117
|
artikel
|
| 60 |
Operation characteristics analyses on a marine-type passive residual heat removal system
|
Wang, Chenyang
|
|
2018
|
120 |
C |
p. 546-558
|
artikel
|
| 61 |
Optimization studies for planning of substitution experiments in the ZED-2 critical facility with plutonium-thorium test fuel
|
Adams, Fred P.
|
|
2018
|
120 |
C |
p. 742-748
|
artikel
|
| 62 |
PIV measurement of cross flow in a rod bundle assisted by telecentric optics and matched index of refraction
|
Xiong, Jinbiao
|
|
2018
|
120 |
C |
p. 540-545
|
artikel
|
| 63 |
Prediction of in-vessel debris bed properties in BWR severe accident scenarios using MELCOR and neural networks
|
Phung, Viet-Anh
|
|
2018
|
120 |
C |
p. 461-476
|
artikel
|
| 64 |
Proposal for the spent nuclear fuel management plan from the decommissioning of Kori site NPPs
|
Seo, Hyung-Woo
|
|
2018
|
120 |
C |
p. 749-762
|
artikel
|
| 65 |
Radiation-induced shear bands enhance softening 316LN austenitic stainless steel
|
Chen, Xudong
|
|
2018
|
120 |
C |
p. 835-838
|
artikel
|
| 66 |
Re-entrainment in and optimization of a vane mist eliminator
|
Mao, Feng
|
|
2018
|
120 |
C |
p. 656-665
|
artikel
|
| 67 |
Research on pressure drop characteristics in inverted half U-tube bundle under two-phase cross-flow condition
|
Zhang, Y.P.
|
|
2018
|
120 |
C |
p. 265-271
|
artikel
|
| 68 |
Resuspension models for monolayer and multilayer deposits of graphite dust
|
Stempniewicz, M.M.
|
|
2018
|
120 |
C |
p. 186-197
|
artikel
|
| 69 |
Safety evaluation of an extended refilling mode operation after the permanent shutdown of a BWR/4 reactor
|
Zhang, Z.W.
|
|
2018
|
120 |
C |
p. 89-99
|
artikel
|
| 70 |
Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors
|
Powers, J.J.
|
|
2018
|
120 |
C |
p. 319-332
|
artikel
|
| 71 |
Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool
|
Coindreau, O.
|
|
2018
|
120 |
C |
p. 880-887
|
artikel
|
| 72 |
149Sm evolution behavior in a small modular molten salt reactor
|
Wu, Jianhui
|
|
2018
|
120 |
C |
p. 100-107
|
artikel
|
| 73 |
Study on the decelerating mechanism of the new control rod hydraulic decelerator for the CRHDS based on numerical simulation and experiment
|
Qin, Benke
|
|
2018
|
120 |
C |
p. 814-827
|
artikel
|
| 74 |
Study on the DLOFC and PLOFC accidents of the 200 MWe pebble-bed modular high temperature gas-cooled reactor with TINTE and SPECTRA codes
|
Zheng, Yanhua
|
|
2018
|
120 |
C |
p. 763-777
|
artikel
|
| 75 |
Supercritical transient analysis in hypothetical fuel-debris systems by multi-region approach based on integral kinetic model
|
Tuya, Delgersaikhan
|
|
2018
|
120 |
C |
p. 169-177
|
artikel
|
| 76 |
The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention
|
Hu, Qiang
|
|
2018
|
120 |
C |
p. 296-303
|
artikel
|
| 77 |
Thermal hydraulic investigations of ALLEGRO ceramic fuel assemblies
|
Orosz, Gergely Imre
|
|
2018
|
120 |
C |
p. 570-580
|
artikel
|
| 78 |
Thermal scattering law of C 2 H 4 n : Integrating experimental data with DFT calculations
|
Ramić, Kemal
|
|
2018
|
120 |
C |
p. 778-787
|
artikel
|
| 79 |
The utilization of thorium in Small Modular Reactors – Part I: Neutronic assessment
|
Akbari-Jeyhouni, Reza
|
|
2018
|
120 |
C |
p. 422-430
|
artikel
|
| 80 |
Treating model defects by fitting smoothly varying model parameters: Energy dependence in nuclear data evaluation
|
Helgesson, P.
|
|
2018
|
120 |
C |
p. 35-47
|
artikel
|
| 81 |
Uncertainty and sensitivity analyses for fuel temperature evaluations of U-Mo/Al plate-type dispersion fuel
|
Sweidan, Faris B.
|
|
2018
|
120 |
C |
p. 581-592
|
artikel
|
| 82 |
Uncertainty assessment on the calculated decay heat of the ASTRID basic design core based on the DARWIN-2.3 package
|
Lebrat, Jean-François
|
|
2018
|
120 |
C |
p. 378-391
|
artikel
|
| 83 |
Unstructured coarse mesh finite difference method to accelerate k-eigenvalue and fixed source neutron transport calculations
|
Zhou, Shengcheng
|
|
2018
|
120 |
C |
p. 367-377
|
artikel
|
| 84 |
Validating the performance of correlated fission multiplicity implementation in radiation transport codes with subcritical neutron multiplication benchmark experiments
|
Arthur, Jennifer
|
|
2018
|
120 |
C |
p. 348-366
|
artikel
|
| 85 |
Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventory
|
Ebiwonjumi, Bamidele
|
|
2018
|
120 |
C |
p. 431-449
|
artikel
|
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