| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A chattering-free sliding mode control strategy for modular high-temperature gas-cooled reactors
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Wang, Guoxu
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133 |
C |
p. 688-695
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artikel
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| 2 |
A comparison of the quantification aspects of human reliability analysis methods in nuclear power plants
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Park, Jooyoung
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133 |
C |
p. 297-312
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artikel
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| 3 |
Adjusted mean generation time parameter in the neutron point kinetics equations
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Diniz, Rodrigo Costa
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133 |
C |
p. 338-346
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artikel
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| 4 |
A facile approach combining the gel-casting with emulsion method for the preparation of high density erbia microspheres
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Gong, Yichao
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133 |
C |
p. 718-722
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artikel
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| 5 |
An accelerated synchronized forward-adjoint approach in method of characteristics neutron transport solution
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Effati, M.
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133 |
C |
p. 820-829
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artikel
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| 6 |
Analysis and application on sensitivity factors of cross validation of fill rate of CPR1000 unit reactor core coolant monitoring system
|
Chen, Yongwei
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133 |
C |
p. 649-657
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artikel
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| 7 |
Analysis of the transmutation of long lived fission products using a charged particle beam
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Hearne, Jason A.
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133 |
C |
p. 501-510
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artikel
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| 8 |
A new and efficient method to measure reactivity in a nuclear reactor
|
Huo, Xingkai
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133 |
C |
p. 455-457
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artikel
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| 9 |
A new approach for solution of time dependent neutron transport equation based on nodal discretization using MCNPX code with feedback
|
Mazaher, Meysam Ghaderi
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133 |
C |
p. 519-526
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artikel
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| 10 |
A new paradigm for breeding of nuclear fuel
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Wallenius, Janne
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133 |
C |
p. 816-819
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artikel
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| 11 |
A novel method for designing the moderator of accelerator-driven neutron source
|
Hu, Guang
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133 |
C |
p. 96-99
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artikel
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| 12 |
A quasi-static approach for the solution of steady-state linear transport problems
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Picca, Paolo
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133 |
C |
p. 805-815
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artikel
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| 13 |
A robust multi phase model to investigate molten material relocation during total flow blockage in SFR fuel subassembly
|
Panigrahi, Prasant Kumar
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133 |
C |
p. 59-72
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artikel
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| 14 |
A smart component methodology for reliability analysis of dynamic systems
|
Shukla, Darpan Krishnakumar
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133 |
C |
p. 863-880
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artikel
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| 15 |
A spatially variant rebalancing method for discrete-ordinates transport equation
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Ford, Wesley
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133 |
C |
p. 589-602
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artikel
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| 16 |
Assembly-level analyses of an innovative long-life marine SMR loaded with accident tolerant fuel
|
Li, Xuezhong
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133 |
C |
p. 227-235
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artikel
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| 17 |
Assessment of the nano-fluid effects on the thermal reactivity feedback coefficients in the VVER-1000 nuclear reactor with nano-fluid as a coolant using thermal hydraulic and neutronics analysis
|
Kianpour, R.
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133 |
C |
p. 623-636
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artikel
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| 18 |
ASTEC simulation of fission product source term ruthenium in coolant in severe accident
|
Hu, Wenchao
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133 |
C |
p. 658-664
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artikel
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| 19 |
A three-dimensional Fourier analysis of fine mesh rebalance acceleration of linear discontinuous sub-cell balance method for diffusion equation on tetrahedral meshes
|
Muhammad, Habib
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133 |
C |
p. 145-153
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artikel
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| 20 |
Code development and characteristics analysis for Leak Before Break in the pipelines of Sodium-cooled Fast Reactor
|
Wu, Di
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133 |
C |
p. 777-794
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artikel
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| 21 |
Comparative methodology between actual RCCS and downscaled heat-removal test facility
|
Takamatsu, Kuniyoshi
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133 |
C |
p. 830-836
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artikel
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| 22 |
Consistent spatial expansion functions on hexagonal surfaces for use in radiation transport methods
|
Zhang, Dingkang
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133 |
C |
p. 603-609
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artikel
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| 23 |
Convergence study of CMFD and lpCMFD acceleration schemes for k-eigenvalue neutron transport problems in 2-D Cartesian geometry with Fourier analysis
|
Chan, Yimeng
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133 |
C |
p. 327-337
|
artikel
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| 24 |
3D containment modeling of PWR-KWU Trillo NPP with the GOTHIC code
|
Fernández-Cosials, Kevin
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133 |
C |
p. 387-399
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artikel
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| 25 |
Deep-learning-based alarm system for accident diagnosis and reactor state classification with probability value
|
Kim, Taek Kyu
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133 |
C |
p. 723-731
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artikel
|
| 26 |
Deep rectifier neural network applied to the accident identification problem in a PWR nuclear power plant
|
Santos, Marcelo Carvalho dos
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133 |
C |
p. 400-408
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artikel
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| 27 |
Deposition characteristic of micro-nano soluble aerosol under bubble scrubbing condition
|
Li, Yingzhi
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133 |
C |
p. 881-888
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artikel
|
| 28 |
Design of an experimental facility with a unit cell test section for studies of the lower plenum in prismatic high temperature gas reactors
|
Landfried, D. Tyler
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133 |
C |
p. 236-247
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artikel
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| 29 |
Design of electric core simulator system (ECSS) for large-scale integral effect test facility
|
Lee, Jewhan
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133 |
C |
p. 762-776
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artikel
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| 30 |
Development and verification of open reactor simulator ADPRES
|
Imron, Muhammad
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133 |
C |
p. 580-588
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artikel
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| 31 |
Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Method and procedure
|
Kim, Kang Seog
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133 |
C |
p. 46-58
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artikel
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| 32 |
Development of the neutronics transport code based on the MOC method and adjoint-forward Coarse Mesh Finite Difference technique: PerMOC code for lattice and whole core calculations
|
Hosseinipour, K.H.
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133 |
C |
p. 84-95
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artikel
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| 33 |
Editorial Board
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133 |
C |
p. ii
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artikel
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| 34 |
Effects of density difference and loading ratio on pebble flow in a three-dimensional two-region-designed pebble bed
|
Wu, Mengqi
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133 |
C |
p. 924-936
|
artikel
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| 35 |
Effects of heat flux on fuel crud deposition and sub-cooled nucleate boiling in simulated PWR primary water at 13 MPa
|
Baek, Seung Heon
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133 |
C |
p. 178-185
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artikel
|
| 36 |
Estimation of probability Density Functions for model input parameters using inverse uncertainty quantification with bias terms
|
Abu Saleem, Rabie A.
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133 |
C |
p. 1-8
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artikel
|
| 37 |
Evaluation of displacement cross-section for neutron-irradiated 15-15Ti steel and its swelling behavior in CiADS radiation environment
|
Korepanova, N.
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133 |
C |
p. 937-949
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artikel
|
| 38 |
Evaluation of durability and radiation shielding property of heavyweight filling material for application in radioactive disposal facilities
|
Kim, Il Sun
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133 |
C |
p. 750-761
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artikel
|
| 39 |
Experimental production and theoretical assessment of 67Cu via neutron induced reaction
|
Karimi, Zahra
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133 |
C |
p. 665-668
|
artikel
|
| 40 |
Experimental study on flow regimes in debris bed formation behavior with mixed-size particles
|
Cheng, Songbai
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133 |
C |
p. 283-296
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artikel
|
| 41 |
Experimental study on the condensation and heat transfer of impinging steam jet on the water surface
|
Cha, Jinho
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133 |
C |
p. 458-468
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artikel
|
| 42 |
Failure mechanism of a prestressed concrete containment vessel in nuclear power plant subjected to accident internal pressure
|
Yan, Jiachuan
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133 |
C |
p. 610-622
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artikel
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| 43 |
Flux distribution of the Superphénix start-up core for the validation of neutronic codes
|
Garcia, E.
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133 |
C |
p. 889-899
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artikel
|
| 44 |
Genetic algorithm for nuclear data evaluation applied to subcritical neutron multiplication inference benchmark experiments
|
Arthur, Jennifer
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133 |
C |
p. 853-862
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artikel
|
| 45 |
Grey relational analysis and optimization of guide vane for reactor coolant pump in the coasting transient process
|
Wang, Xiuli
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133 |
C |
p. 431-440
|
artikel
|
| 46 |
Improvement of horizontal stratification criteria in the SPACE code
|
Lee, Jong Hyuk
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133 |
C |
p. 122-128
|
artikel
|
| 47 |
Influence of corium composition on ex-vessel steam explosion
|
Skobe, Tomaž
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133 |
C |
p. 359-377
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artikel
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| 48 |
Integrating a multi-layer deformation model in FRAPTRAN for accident Tolerant fuel analysis
|
He, Yanan
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133 |
C |
p. 441-454
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artikel
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| 49 |
Investigation on the mechanism of the immobilization of CeO2 by using cullet-based glass (CBG)
|
Wang, Zhongbing
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133 |
C |
p. 209-215
|
artikel
|
| 50 |
Large eddy simulation on the turbulent flow and mixing in a 2 × 2 rod bundle
|
Wang, Han
|
|
|
133 |
C |
p. 549-561
|
artikel
|
| 51 |
Methodology for thermal analysis of spent nuclear fuel dry cask using CFD codes
|
Benavides, Julio
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133 |
C |
p. 257-274
|
artikel
|
| 52 |
Modeling a fast spectrum molten salt reactor in a systems dynamics fuel cycles code
|
Davidson, E.
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133 |
C |
p. 409-424
|
artikel
|
| 53 |
Modification and update of FROBA-ROD code and its applications in fuel rod behavior analysis for PWRs
|
Liao, Haoyu
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133 |
C |
p. 900-915
|
artikel
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| 54 |
Neutron flux distribution and conversion ratio of Critical Experiment Device for molten salt reactor research
|
Liu, Yafen
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133 |
C |
p. 707-717
|
artikel
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| 55 |
Neutronic and thermal-hydraulic aspects of loading pattern optimization during the first cycle of VVER-1000 reactor using Polar Bear Optimization method
|
Aghili Nasr, Mahdi
|
|
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133 |
C |
p. 538-548
|
artikel
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| 56 |
Neutron multiplication and fissile material distribution in a nuclear reactor
|
Saracco, P.
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|
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133 |
C |
p. 696-706
|
artikel
|
| 57 |
Numerical simulation and experimental investigation of heat pipe heat exchanger applied in residual heat removal system
|
Xie, Chuan-Yang
|
|
|
133 |
C |
p. 568-579
|
artikel
|
| 58 |
Numerical study of bubble rising in quiescent liquid under rolling motion conditions using MPS – MAFL method
|
Basit, Muhammad Abdul
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|
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133 |
C |
p. 469-482
|
artikel
|
| 59 |
Numerical study of heat transfer in ascending mixed convection with internal heat generation
|
Kasam, Alisha
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133 |
C |
p. 138-144
|
artikel
|
| 60 |
Numerical study of hyperstoichiometric fuel creep (UO2+ x ) in fuel clad interaction of WWER1000
|
Safari, M.
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|
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133 |
C |
p. 950-959
|
artikel
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| 61 |
On an analytical solution for the two energy group neutron space-kinetic equation in heterogeneous cylindrical geometry
|
Oliveira, F.R.
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|
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133 |
C |
p. 216-220
|
artikel
|
| 62 |
Performance evaluation of decay heat removal systems of Fluoride-salt-cooled High-temperature Reactor (FHR)
|
Nakata, Junya
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133 |
C |
p. 248-256
|
artikel
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| 63 |
Performance evaluation of modified Gaussian and Lagrangian models under low wind speed: A case study
|
Rakesh, P.T.
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133 |
C |
p. 562-567
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artikel
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| 64 |
Perturbation and sensitivity calculations for time eigenvalues using the Generalized Iterated Fission Probability
|
Jinaphanh, A.
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|
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133 |
C |
p. 678-687
|
artikel
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| 65 |
Photon and neutron hybrid transmutation for radioactive cesium and iodine
|
Rehman, Haseeb ur
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133 |
C |
p. 527-537
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artikel
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| 66 |
Quantification and propagation of neutronics uncertainties of the Kozloduy-6 VVER-1000 fuel assembly using SCALE 6.2.1 within the NEA/OECD benchmark for uncertainty analysis in modelling of LWRs
|
Nyalunga, G.P.
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133 |
C |
p. 732-749
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artikel
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| 67 |
Quasi-random discrete ordinates method for neutron transport problems
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de Almeida Konzen, Pedro Henrique
|
|
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133 |
C |
p. 275-282
|
artikel
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| 68 |
Rapid nuclide identification algorithm based on convolutional neural network
|
Liang, Dajian
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133 |
C |
p. 483-490
|
artikel
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| 69 |
γ-Ray spectral analysis method for real-time detection of fuel element failure
|
Qin, Guoxiu
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133 |
C |
p. 221-226
|
artikel
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| 70 |
Research of parameter distributing simulation and modeling for the condenser in nuclear power plant
|
Gong, Meijie
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133 |
C |
p. 313-326
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artikel
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| 71 |
Research on thermal behaviors of several accident tolerant fuels based on 5 × 5 bundle subchannel model
|
Cai, Jiejin
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133 |
C |
p. 9-20
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artikel
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| 72 |
RETRACTED: Core design and analysis of a lead-bismuth cooled small modular reactor
|
Wang, Chenglong
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133 |
C |
p. 511-518
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artikel
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| 73 |
RMC/CTF multiphysics solutions to VERA core physics benchmark problem 9
|
Ma, Yugao
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133 |
C |
p. 837-852
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artikel
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| 74 |
ROSA/LSTF test and RELAP5 code analyses on primary feed-and-bleed operation during total loss-of-feedwater transient of PWR
|
Takeda, Takeshi
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133 |
C |
p. 194-201
|
artikel
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| 75 |
Scenario options to calculation of Derived Concentration Guideline Levels for a multi-unit decommissioning site
|
Seo, Hyung-Woo
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133 |
C |
p. 347-358
|
artikel
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| 76 |
Sensitivity analysis of in-vessel accident progression behavior in Fukushima Daiichi Nuclear Power Plant Unit 3
|
Li, Xin
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133 |
C |
p. 21-34
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artikel
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| 77 |
Simulation study on flow instability in parallel narrow rectangular channels for downward flow with different heating modes
|
Zhang, Xue
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133 |
C |
p. 669-677
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artikel
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| 78 |
Spatially-dependent nuclear reactor kinetic calculations with the explicit fission product model
|
Katagiri, Koji
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133 |
C |
p. 202-208
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artikel
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| 79 |
Study on the transient evolution law of internal flow field and dynamic stress of reactor coolant pump under rotor seizure accident
|
Wang, Xiuli
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133 |
C |
p. 35-45
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artikel
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| 80 |
Teaching-learning based optimization algorithm for core reload pattern optimization of a research reactor
|
Ammar, Ahmad
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133 |
C |
p. 169-177
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artikel
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| 81 |
Theoretical investigations on flow-induced vibration of fuel rods with spacer grids in axial flow
|
Liu, Pengliang
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133 |
C |
p. 916-923
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artikel
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| 82 |
The release of carbon-14 from irradiated PGA graphite by thermal treatment in air
|
Metcalfe, M.P.
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133 |
C |
p. 110-121
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artikel
|
| 83 |
Thermal and mechanical properties of U3Si and USi3
|
Mohamad, Afiqa
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133 |
C |
p. 186-193
|
artikel
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| 84 |
Toward a better thermal scattering law of (C5O2H8)n: Inelastic neutron scattering and oClimax + NJOY2016
|
Ramić, Kemal
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133 |
C |
p. 425-430
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artikel
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| 85 |
Two-step Monte Carlo sensitivity analysis of alpha- and gamma-eigenvalues with the differential operator sampling method
|
Yamamoto, Toshihiro
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133 |
C |
p. 100-109
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artikel
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| 86 |
Ultrasonic high frequency guided wave for detection and identification of defect location in seal welds of sodium cooled fast reactor fuel subassemblies
|
Dhayalan, R.
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133 |
C |
p. 795-804
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artikel
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| 87 |
Uncertainty quantification for the first-cycle modeling and simulations of the BEAVRS benchmark problem
|
Wan, Chenghui
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133 |
C |
p. 378-386
|
artikel
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| 88 |
Uncertainty quantification of the SPND dynamic model based on non-intrusive polynomial chaos method
|
Peng, Xingjie
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133 |
C |
p. 73-83
|
artikel
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| 89 |
Validation of a thermo-fluid-structure coupling approach for RPV creep failure analysis against FOREVER-EC2 experiment
|
Yu, Peng
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133 |
C |
p. 637-648
|
artikel
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| 90 |
Verification of a HC-PK-CFD coupled program based a benchmark on beam trip transients for XADS reactor
|
Gu, Zhixing
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133 |
C |
p. 491-500
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artikel
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| 91 |
Verification of DeCART2D/CAPP code system for VHTR analysis with PMR-200 benchmark
|
Jeong, Eun
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133 |
C |
p. 154-168
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artikel
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| 92 |
Wilks’ formula applied to computational tools: A practical discussion and verification
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Porter, N.W.
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133 |
C |
p. 129-137
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artikel
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