| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A framework to estimate probability of diagnosis error in NPP advanced MCR
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Kim, Ar Ryum
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111 |
C |
p. 31-40
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artikel
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| 2 |
A modified power method for the multilayer multigroup two-dimensional neutron diffusion equation
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Zanette, R.
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111 |
C |
p. 136-140
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artikel
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| 3 |
Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code
|
Jo, Yunki
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111 |
C |
p. 141-151
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artikel
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| 4 |
Analysis of thorium fuel feasibility in large scale gas cooled fast reactor using MCNPX code
|
Ibrahim, Amr
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111 |
C |
p. 460-467
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artikel
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| 5 |
A Newton solution for the Superhomogenization method: The PJFNK-SPH
|
Ortensi, Javier
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111 |
C |
p. 579-594
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artikel
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| 6 |
A non-equilibrium relaxation model for fast depressurization of pipelines
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Nouri-Borujerdi, A.
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111 |
C |
p. 1-11
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artikel
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| 7 |
A novel framework for intelligent signal detection via artificial neural networks for cyclic voltammetry in pyroprocessing technology
|
Rakhshan Pouri, Samaneh
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111 |
C |
p. 242-254
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artikel
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| 8 |
Application of metaheuristics to Loading Pattern Optimization problems based on the IAEA-3D and BIBLIS-2D data
|
Meneses, Anderson Alvarenga de Moura
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111 |
C |
p. 329-339
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artikel
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| 9 |
A scenario analysis of once-through thorium fuel cycles with pressure tube HWRs in Canada
|
Wojtaszek, D.
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111 |
C |
p. 152-162
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artikel
|
| 10 |
A study on the lift-off diameter of bubbles generated on horizontal tube
|
Ryu, Sung Uk
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111 |
C |
p. 303-310
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artikel
|
| 11 |
Availability analysis of safety grade multiple redundant controller used in advanced nuclear safety systems
|
Son, Kwang Seop
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111 |
C |
p. 73-81
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artikel
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| 12 |
Corrigendum to “Fuzzy probability based fault tree analysis to propagate and quantify epistemic uncertainty” [Ann. Nucl. Energy 85 (2015) 1189–1199]
|
Purba, Julwan Hendry
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111 |
C |
p. 716-717
|
artikel
|
| 13 |
Corrigendum to “Optimal design methods for a digital human-computer interface based on human reliability in a nuclear power plant: Part 2: The optimization design method for component quantity” [Ann. Nucl. Energy 106 (2017) 247–255]
|
Jiang, Jianjun
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111 |
C |
p. 715
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artikel
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| 14 |
Design and criticality analysis of colloidal slurry nuclear reactors
|
Laramore, Diego
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111 |
C |
p. 255-261
|
artikel
|
| 15 |
Design of a passive safety system for a nuclear thermal rocket
|
Khatry, Jivan
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|
111 |
C |
p. 536-553
|
artikel
|
| 16 |
Design parameters in an annular, prismatic HTGR for passive decay heat removal
|
Sambuu, Odmaa
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111 |
C |
p. 441-448
|
artikel
|
| 17 |
Development of an EEG-based workload measurement method in nuclear power plants
|
Choi, Moon Kyoung
|
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|
111 |
C |
p. 595-607
|
artikel
|
| 18 |
Development of emergency planning zone for high temperature gas-cooled reactor
|
Ding, Hongchun
|
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111 |
C |
p. 347-353
|
artikel
|
| 19 |
Development of Nuclear Safety Culture evaluation method for an operation team based on the probabilistic approach
|
Han, Sang Min
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111 |
C |
p. 317-328
|
artikel
|
| 20 |
3D numerical modeling of liquid metal turbulent flow in an annular linear induction pump
|
Abdullina, K.I.
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111 |
C |
p. 118-126
|
artikel
|
| 21 |
Droplet phase change model and its application in wave-type vanes of steam generator
|
Zhao, Fulong
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|
111 |
C |
p. 176-187
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artikel
|
| 22 |
Editorial board
|
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|
111 |
C |
p. IFC
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artikel
|
| 23 |
Estimation of reactivity and delayed neutron precursors’ concentrations using a multiscale extended Kalman filter
|
Patel, Shrenik B.
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|
111 |
C |
p. 666-675
|
artikel
|
| 24 |
Evaluation of neutron flux and fission rate distributions inside the JSI TRIGA Mark II reactor using multiple in-core fission chambers
|
Goričanec, Tanja
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111 |
C |
p. 407-440
|
artikel
|
| 25 |
Experimental study on debris bed characteristics for the sedimentation behavior of solid particles used as simulant debris
|
Shamsuzzaman, M.
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111 |
C |
p. 474-486
|
artikel
|
| 26 |
Experimental study on heat transfer of supercritical water flowing upward and downward in 2×2 rod bundle with wrapped wire
|
Hu, Z.X.
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111 |
C |
p. 50-58
|
artikel
|
| 27 |
Fast solution of neutron diffusion problem by reduced basis finite element method
|
Chunyu, Zhang
|
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|
111 |
C |
p. 702-708
|
artikel
|
| 28 |
Flexibility of ADS for minor actinides transmutation in different two-stage PWR-ADS fuel cycle scenarios
|
Zhou, Shengcheng
|
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111 |
C |
p. 271-279
|
artikel
|
| 29 |
Fuel conditioning facility inert gas filled reprocessing hot cell leak rate measurement
|
Pope, Chad L.
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|
111 |
C |
p. 676-682
|
artikel
|
| 30 |
Fuel cycles optimization of nuclear power industry in China
|
Yue, Qiang
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|
111 |
C |
p. 635-643
|
artikel
|
| 31 |
Heat removal ability for different orientations of single-phase natural circulation loops using the entransy method
|
Goudarzi, N.
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111 |
C |
p. 509-522
|
artikel
|
| 32 |
Higher order power reactor noise analysis: The multigroup diffusion model
|
Ayyoubzadeh, Seyed Mohsen
|
|
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111 |
C |
p. 354-370
|
artikel
|
| 33 |
Impact of impurity in transmutation cycle on neutronics design of revised accelerator-driven system
|
Sugawara, Takanori
|
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111 |
C |
p. 449-459
|
artikel
|
| 34 |
Investigation of the density wave oscillation in ocean motions with reduced order models
|
Yan, B.H.
|
|
|
111 |
C |
p. 262-270
|
artikel
|
| 35 |
Large eddy simulation on turbulent heat transfer in reactor vessel lower head corium pools
|
Zhang, Luteng
|
|
|
111 |
C |
p. 293-302
|
artikel
|
| 36 |
Linear active disturbance rejection control for pressurized water reactor power
|
Liu, Yuyan
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|
111 |
C |
p. 22-30
|
artikel
|
| 37 |
Measurement and analysis of 232Th(n,2n)231Th reaction rate in the thorium oxide cylinder with a D-T neutron source
|
Liu, Zhujun
|
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|
111 |
C |
p. 660-665
|
artikel
|
| 38 |
Modeling neutron count distribution in a subcritical core by stochastic differential equations
|
Dubi, Chen
|
|
|
111 |
C |
p. 608-615
|
artikel
|
| 39 |
Modelling horizontal two-phase flows using generalized models
|
Höhne, Thomas
|
|
|
111 |
C |
p. 311-316
|
artikel
|
| 40 |
Multiscale subspace identification of nuclear reactor using wavelet basis function
|
Vajpayee, Vineet
|
|
|
111 |
C |
p. 280-292
|
artikel
|
| 41 |
Multivariable modeling and nonlinear coordination control of nuclear reactor cores with/without xenon oscillation using H∞ loop shaping approach
|
Li, Gang
|
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|
111 |
C |
p. 82-100
|
artikel
|
| 42 |
Multivariate algorithms for initiating event detection and identification in nuclear power plants
|
Wu, Shun-Chi
|
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|
111 |
C |
p. 127-135
|
artikel
|
| 43 |
Neutron multiplication in random media: Reactivity and kinetics parameters
|
Larmier, Coline
|
|
|
111 |
C |
p. 391-406
|
artikel
|
| 44 |
Numerical investigation of the separation performance of full-scale AP1000 steam-water separator
|
Zhao, Fulong
|
|
|
111 |
C |
p. 204-223
|
artikel
|
| 45 |
Numerical study of air ingress transition to natural circulation in a high temperature helium loop
|
Franken, Daniel
|
|
|
111 |
C |
p. 371-378
|
artikel
|
| 46 |
On the effect of conjugate heat transfer on turbulence in supercritical fluids: Results from a LES application
|
Pucciarelli, Andrea
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|
|
111 |
C |
p. 340-346
|
artikel
|
| 47 |
On-the-fly treatment of temperature dependent cross sections in the unresolved resonance region in RMC code
|
Liu, Shichang
|
|
|
111 |
C |
p. 234-241
|
artikel
|
| 48 |
On the stability of linear fractional-space neutron point kinetics (F-SNPK) models for nuclear reactor dynamics
|
Vyawahare, Vishwesh A.
|
|
|
111 |
C |
p. 12-21
|
artikel
|
| 49 |
Practical environment-corrected discontinuity factors and homogenized parameters for improved PT-SCWR neutron diffusion solutions
|
Sharpe, J.R.
|
|
|
111 |
C |
p. 101-117
|
artikel
|
| 50 |
Predicting spatially dependent reaction rate for problem with nonuniform temperature distribution by subgroup method
|
He, Qingming
|
|
|
111 |
C |
p. 188-203
|
artikel
|
| 51 |
Random geometry capability in RMC code for explicit analysis of polytype particle/pebble and applications to HTR-10 benchmark
|
Liu, Shichang
|
|
|
111 |
C |
p. 41-49
|
artikel
|
| 52 |
Research on flow field characteristics and force analysis of fuel elements pneumatic transportation in a pebble bed reactor
|
Liu, Hongbing
|
|
|
111 |
C |
p. 568-578
|
artikel
|
| 53 |
Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors
|
Seo, Seok Bin
|
|
|
111 |
C |
p. 554-567
|
artikel
|
| 54 |
Safety parameter display performance in a computer simulated PWR
|
dos Santos, Matheus Prim Markoski
|
|
|
111 |
C |
p. 468-473
|
artikel
|
| 55 |
Sensitivity analysis of VERA-CS and FRAPCON coupling in a multiphysics environment
|
Blakely, Cole
|
|
|
111 |
C |
p. 683-701
|
artikel
|
| 56 |
Spatial effects in low neutron source start-up and associated stochastic phenomena
|
Williams, M.M.R.
|
|
|
111 |
C |
p. 616-634
|
artikel
|
| 57 |
Study on the algorithm for solving two-fluid seven-equation two-pressure model
|
Chao, Fei
|
|
|
111 |
C |
p. 379-390
|
artikel
|
| 58 |
Thermal stratification and mixing in a suppression pool induced by direct steam injection
|
Li, Hua
|
|
|
111 |
C |
p. 487-498
|
artikel
|
| 59 |
The study of passive cooling system assisted with separate heat pipe for decay heat removal in spent fuel pool
|
Lai, Kun
|
|
|
111 |
C |
p. 523-535
|
artikel
|
| 60 |
Thorium-based mixed oxide fuel in a pressurized water reactor: A burnup analysis with MCNP
|
Tucker, Lucas P.
|
|
|
111 |
C |
p. 163-175
|
artikel
|
| 61 |
Validation and uncertainty quantification for FEBA, FLECHT–SEASET, and PERICLES tests incorporating multi-scaling effects
|
Heo, Jaeseok
|
|
|
111 |
C |
p. 499-508
|
artikel
|
| 62 |
Validation of LOOP through PWR measured data
|
Gul, Anas
|
|
|
111 |
C |
p. 224-233
|
artikel
|
| 63 |
Validation of SuperMC with BEAVRS benchmark at hot zero power condition
|
Wang, Zhiyan
|
|
|
111 |
C |
p. 709-714
|
artikel
|
| 64 |
Validation of the MC2-3/TWODANT/DIF3D code system for control rod worth via BFS-75-1 and BFS-109-2A reactor physics experiments
|
Yun, Sunghwan
|
|
|
111 |
C |
p. 59-72
|
artikel
|
| 65 |
Vanadium, rhodium, silver and cobalt self-powered neutron detector calculations by RAST-K v2.0
|
Khoshahval, Farrokh
|
|
|
111 |
C |
p. 644-659
|
artikel
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