| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Adsorption of uranium(VI) from sulphate solutions using Amberlite IRA-402 resin: Equilibrium, kinetics and thermodynamics study
|
Solgy, Mostafa
|
|
2015
|
75 |
C |
p. 132-138
|
artikel
|
| 2 |
Analysis of anticipated transient without scram of a Super Fast Reactor with single flow pass core
|
Sutanto,
|
|
2015
|
75 |
C |
p. 54-63
|
artikel
|
| 3 |
Analysis of flow and heat transfer in a new lattice
|
Xiao, Hongguang
|
|
2015
|
75 |
C |
p. 536-541
|
artikel
|
| 4 |
Analysis of Phenix End-of-Life asymmetry test with multi-dimensional pool modeling of MARS-LMR code
|
Jeong, H.-Y.
|
|
2015
|
75 |
C |
p. 443-451
|
artikel
|
| 5 |
Analysis on isotopic plutonium barrier based on spent nuclear fuel of LWR
|
Permana, Sidik
|
|
2015
|
75 |
C |
p. 116-122
|
artikel
|
| 6 |
A new mathematical adjoint for the modified SAAF- S N equations
|
Schunert, Sebastian
|
|
2015
|
75 |
C |
p. 340-352
|
artikel
|
| 7 |
A new methodology for estimation of initial entrainment fraction in annular flow for improved dryout prediction
|
Dasgupta, A.
|
|
2015
|
75 |
C |
p. 323-330
|
artikel
|
| 8 |
Application of Continuous and Structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event
|
Demeshko, M.
|
|
2015
|
75 |
C |
p. 645-657
|
artikel
|
| 9 |
AP1000® SBLOCA simulations with TRACE code
|
Montero-Mayorga, J.
|
|
2015
|
75 |
C |
p. 87-100
|
artikel
|
| 10 |
A unified generic theory on discontinuity factors in diffusion, SP3 and transport calculations
|
Yu, Lulin
|
|
2015
|
75 |
C |
p. 239-248
|
artikel
|
| 11 |
BRAHMMA: A compact experimental accelerator driven subcritical facility using D-T/D-D neutron source
|
Sinha, Amar
|
|
2015
|
75 |
C |
p. 590-594
|
artikel
|
| 12 |
CFD analysis of flow and heat transfer in Canadian supercritical water reactor bundle
|
Podila, K.
|
|
2015
|
75 |
C |
p. 1-10
|
artikel
|
| 13 |
CHF prediction model research for flat and hypervapotron heating surface in subcooled flow nucleate boiling
|
Lin, Meng
|
|
2015
|
75 |
C |
p. 581-589
|
artikel
|
| 14 |
Commercial thorium fuel manufacture and irradiation: Testing (Th,Pu) O 2 and (Th,U) O 2 in the “Seven-Thirty” program
|
Insulander Björk, Klara
|
|
2015
|
75 |
C |
p. 79-86
|
artikel
|
| 15 |
Comparison of algorithms for Doppler broadening pointwise tabulated cross sections
|
Romano, Paul K.
|
|
2015
|
75 |
C |
p. 358-364
|
artikel
|
| 16 |
Conceptual design of a passively safe thorium breeder Pebble Bed Reactor
|
Wols, F.J.
|
|
2015
|
75 |
C |
p. 542-558
|
artikel
|
| 17 |
Coupling of system thermal–hydraulics and Monte-Carlo code: Convergence criteria and quantification of correlation between statistical uncertainty and coupled error
|
Wu, Xu
|
|
2015
|
75 |
C |
p. 377-387
|
artikel
|
| 18 |
Critical flow maps using an extended Henry–Fauske model
|
Kim, Yeon-Sik
|
|
2015
|
75 |
C |
p. 516-520
|
artikel
|
| 19 |
Critical mass calculations using MCNP: An academic exercise
|
Kastanya, Doddy
|
|
2015
|
75 |
C |
p. 228-231
|
artikel
|
| 20 |
CUDA and MPI performances on the computation of Rossi-α distribution from pulsed neutron sources
|
Talamo, Alberto
|
|
2015
|
75 |
C |
p. 168-175
|
artikel
|
| 21 |
Detailed evaluation of melt pool configuration in the lower plenum of the APR1400 reactor vessel during severe accidents
|
Park, Rae-Joon
|
|
2015
|
75 |
C |
p. 476-482
|
artikel
|
| 22 |
Determination of total mass attenuation coefficients, effective atomic numbers and electron densities for different shielding materials
|
Elmahroug, Y.
|
|
2015
|
75 |
C |
p. 268-274
|
artikel
|
| 23 |
Development of a phenomena identification ranking table for simulating a station blackout transient of a pressurized water reactor with a thermal-hydraulic integral effect test facility
|
Kang, Kyoung-Ho
|
|
2015
|
75 |
C |
p. 72-78
|
artikel
|
| 24 |
Development of semi-empirical model for tritium permeation under non-uniform temperature distribution at heat exchanger tube wall
|
Park, Min Young
|
|
2015
|
75 |
C |
p. 413-420
|
artikel
|
| 25 |
Dry storage of spent nuclear fuel in UAE – Economic aspect
|
Al Saadi, Sara
|
|
2015
|
75 |
C |
p. 527-535
|
artikel
|
| 26 |
3D simulations of the hydrodynamic deformation of melt droplets in a water pool
|
Thakre, Sachin
|
|
2015
|
75 |
C |
p. 123-131
|
artikel
|
| 27 |
Editorial board
|
|
|
2015
|
75 |
C |
p. IFC
|
artikel
|
| 28 |
Editors’ note
|
Williams, M.M.R.
|
|
2015
|
75 |
C |
p. 752
|
artikel
|
| 29 |
Effect of geometric factors on performance of a sodium to air heat exchanger in a fast breeder reactor
|
Kannan, K.
|
|
2015
|
75 |
C |
p. 428-437
|
artikel
|
| 30 |
Estimation of neutronics parameter sensitivity to nuclear data in random sampling-based uncertainty quantification calculations
|
Chiba, Go
|
|
2015
|
75 |
C |
p. 395-403
|
artikel
|
| 31 |
Evaluation of interfacial area transport equation in vertical bubbly two-phase flow in large diameter pipes
|
Tian, Daogui
|
|
2015
|
75 |
C |
p. 199-209
|
artikel
|
| 32 |
Evaluation of parameterization schemes in the Weather Research and Forecasting (WRF) model: A case study for the Kaiga nuclear power plant site
|
Shrivastava, R.
|
|
2015
|
75 |
C |
p. 693-702
|
artikel
|
| 33 |
Experimental investigation of void distribution in suppression pool over the duration of a loss of coolant accident using steam–water two-phase mixture
|
Rassame, Somboon
|
|
2015
|
75 |
C |
p. 570-580
|
artikel
|
| 34 |
Experimental investigation on pressure oscillation frequency for submerged sonic/supersonic steam jet
|
Qiu, Binbin
|
|
2015
|
75 |
C |
p. 388-394
|
artikel
|
| 35 |
Experimental research on the thermal hydraulic characteristics of liquid sodium flowing in annuli with low Peclet number
|
Qiu, Zicheng
|
|
2015
|
75 |
C |
p. 483-491
|
artikel
|
| 36 |
Experimental validation of RELAP5 predictions for subcooled leak flow through narrow circumferential slits
|
Ghosh, Sandip
|
|
2015
|
75 |
C |
p. 507-515
|
artikel
|
| 37 |
Explicit appropriate basis function method for numerical solution of stiff systems
|
Chen, Wenzhen
|
|
2015
|
75 |
C |
p. 353-357
|
artikel
|
| 38 |
Features of a subcritical nuclear reactor
|
Vega-Carrillo, Hector Rene
|
|
2015
|
75 |
C |
p. 101-106
|
artikel
|
| 39 |
Higher order sliding mode controller design for a research nuclear reactor considering the effect of xenon concentration during load following operation
|
Ansarifar, G.R.
|
|
2015
|
75 |
C |
p. 728-735
|
artikel
|
| 40 |
Investigation of molten core–concrete interaction reactor benchmark test for VVER 1000
|
Stefanova, A.
|
|
2015
|
75 |
C |
p. 742-751
|
artikel
|
| 41 |
Investigation of the Self-Interrogation Neutron Resonance Densitometry applied to spent fuel using Monte Carlo simulations
|
Rossa, Riccardo
|
|
2015
|
75 |
C |
p. 176-183
|
artikel
|
| 42 |
Investigation of trans-critical CO2 horizontal mini-channel flow with multi-peak heat transfer behaviors
|
Chen, Lin
|
|
2015
|
75 |
C |
p. 559-569
|
artikel
|
| 43 |
Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor
|
Tusheva, P.
|
|
2015
|
75 |
C |
p. 249-260
|
artikel
|
| 44 |
Linkage options between unit process to enhance proliferation resistance of pyroprocessing
|
Ahn, Seong-Kyu
|
|
2015
|
75 |
C |
p. 184-188
|
artikel
|
| 45 |
Measurement of multiple α-modes at the Delphi subcritical assembly by neutron noise techniques
|
Szieberth, Máté
|
|
2015
|
75 |
C |
p. 146-157
|
artikel
|
| 46 |
Methodology for the scoping assessment of radioactive releases during dismantling of RBMK-1500 reactor systems with low-level contamination
|
Ragaišis, Valdas
|
|
2015
|
75 |
C |
p. 193-198
|
artikel
|
| 47 |
Modeling droplet-laden flows in moisture separators using k-d trees
|
Zhang, Huang
|
|
2015
|
75 |
C |
p. 452-461
|
artikel
|
| 48 |
Modeling scheme of the Safety Injection Tank with Fluidic Device for best estimate calculation of LBLOCA
|
Bang, Young Seok
|
|
2015
|
75 |
C |
p. 605-610
|
artikel
|
| 49 |
Monte Carlo methods for reactor period calculations
|
Zoia, Andrea
|
|
2015
|
75 |
C |
p. 627-634
|
artikel
|
| 50 |
Multicriteria decision analysis based on analytic hierarchy process in GIS environment for siting nuclear power plant in Egypt
|
Abudeif, A.M.
|
|
2015
|
75 |
C |
p. 682-692
|
artikel
|
| 51 |
Negative pressure difference evaluation of Lungmen ABWR containment by using GOTHIC
|
Chen, Yen-Shu
|
|
2015
|
75 |
C |
p. 672-681
|
artikel
|
| 52 |
Neutron batch size optimisation methodology for Monte Carlo criticality calculations
|
Tuttelberg, Kaur
|
|
2015
|
75 |
C |
p. 620-626
|
artikel
|
| 53 |
Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors
|
George, Nathan Michael
|
|
2015
|
75 |
C |
p. 703-712
|
artikel
|
| 54 |
Neutronic parameters of a low enrichment core in reactor LR-0 for MSR research
|
Košt’ál, Michal
|
|
2015
|
75 |
C |
p. 316-322
|
artikel
|
| 55 |
Neutronics calculations for denatured molten salt reactors: Assessing resource requirements and proliferation-risk attributes
|
Ahmad, Ali
|
|
2015
|
75 |
C |
p. 261-267
|
artikel
|
| 56 |
Neutron irradiation performance of Zircaloy-4 under research reactor operating conditions
|
Jin, Hyun Ju
|
|
2015
|
75 |
C |
p. 309-315
|
artikel
|
| 57 |
Neutron kerma coefficients of compounds for shielding and dosimetry
|
Singh, Vishwanath P.
|
|
2015
|
75 |
C |
p. 189-192
|
artikel
|
| 58 |
Novel passive and active tungsten-based identifiers for maintaining the continuity of knowledge of spent nuclear fuel copper canisters
|
Chernikova, Dina
|
|
2015
|
75 |
C |
p. 219-227
|
artikel
|
| 59 |
Nuclear data sensitivity and uncertainty for the Canadian supercritical water-cooled reactor II: Full core analysis
|
Langton, S.E.
|
|
2015
|
75 |
C |
p. 635-644
|
artikel
|
| 60 |
Nuclear waste transmutation performance assessment of an accelerator driven subcritical reactor for waste transmutation (ADS-NWT)
|
Chen, Zhong
|
|
2015
|
75 |
C |
p. 723-727
|
artikel
|
| 61 |
Numerical simulation of temperature fluctuation reduction by a vortex breaker in an elbow pipe with thermal stratification
|
Lu, T.
|
|
2015
|
75 |
C |
p. 462-467
|
artikel
|
| 62 |
NUSS: A tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling method
|
Zhu, Ting
|
|
2015
|
75 |
C |
p. 713-722
|
artikel
|
| 63 |
On the second moment of a stochastic radiation field
|
Ayyoubzadeh, Seyed Mohsen
|
|
2015
|
75 |
C |
p. 283-291
|
artikel
|
| 64 |
Operation characteristic of Integrated Pressurized Water Reactor under coordination control scheme
|
Du, Xue
|
|
2015
|
75 |
C |
p. 658-664
|
artikel
|
| 65 |
Optimization method for the design of hexagonal fuel assemblies
|
Qvist, Staffan
|
|
2015
|
75 |
C |
p. 498-506
|
artikel
|
| 66 |
Parameterized representation of macroscopic cross section for PWR reactor
|
Fiel, João Cláudio Batista
|
|
2015
|
75 |
C |
p. 736-741
|
artikel
|
| 67 |
Preliminary studies of compact Brayton cycle performance for Small Modular High Temperature Gas-cooled Reactor system
|
Bae, Seong Jun
|
|
2015
|
75 |
C |
p. 11-19
|
artikel
|
| 68 |
Pressurized water reactor in-core nuclear fuel management by tabu search
|
Hill, Natasha J.
|
|
2015
|
75 |
C |
p. 64-71
|
artikel
|
| 69 |
Prototypic corium oxidation and hydrogen release during the Fuel–Coolant Interaction
|
Tyrpekl, Vaclav
|
|
2015
|
75 |
C |
p. 210-218
|
artikel
|
| 70 |
Publisher Note
|
|
|
2015
|
75 |
C |
p. iii
|
artikel
|
| 71 |
Quantification of in-containment fission products source term for 1000MWe PWR under loss of coolant accident
|
Mehboob, Khurram
|
|
2015
|
75 |
C |
p. 365-376
|
artikel
|
| 72 |
Radiocarbon mass balance for a Magnox nuclear power station
|
Metcalfe, M.P.
|
|
2015
|
75 |
C |
p. 665-671
|
artikel
|
| 73 |
Research of flow instability in OTSG under low load conditions
|
Xia, Genglei
|
|
2015
|
75 |
C |
p. 421-427
|
artikel
|
| 74 |
Safety, security and safeguard
|
Zakariya, Nasiru Imam
|
|
2015
|
75 |
C |
p. 292-302
|
artikel
|
| 75 |
Scaling analysis for the ocean motions in single phase natural circulation
|
Yan, B.H.
|
|
2015
|
75 |
C |
p. 521-526
|
artikel
|
| 76 |
Seed and blanket thorium-reprocessed fuel ADS: Multi-cycle approach for higher thorium utilization and TRU transmutation
|
Vu, Thanh Mai
|
|
2015
|
75 |
C |
p. 438-442
|
artikel
|
| 77 |
Sensitivity and uncertainty analysis for UO 2 and MOX fueled PWR cells
|
Foad, Basma
|
|
2015
|
75 |
C |
p. 595-604
|
artikel
|
| 78 |
Simulation of boiling flow in evaporator of separate type heat pipe with low heat flux
|
Kuang, Y.W.
|
|
2015
|
75 |
C |
p. 158-167
|
artikel
|
| 79 |
Sliding mode control design for a PWR nuclear reactor using sliding mode observer during load following operation
|
Ansarifar, G.R.
|
|
2015
|
75 |
C |
p. 611-619
|
artikel
|
| 80 |
Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems
|
Nikitin, E.
|
|
2015
|
75 |
C |
p. 492-497
|
artikel
|
| 81 |
Study of power distribution in the CZP, HFP and normal operation states of VVER-1000 (Bushehr) nuclear reactor core by coupling nuclear codes
|
Rafiei Karahroudi, Mohsen
|
|
2015
|
75 |
C |
p. 38-43
|
artikel
|
| 82 |
Subchannel analysis of fuel temperature and departure of nucleate boiling of TRIGA Mark I
|
Johns, Jesse
|
|
2015
|
75 |
C |
p. 331-339
|
artikel
|
| 83 |
The effect of changing enrichments on core performance
|
Levine, S.
|
|
2015
|
75 |
C |
p. 139-145
|
artikel
|
| 84 |
The effect of coolant quantity on local fuel–coolant interactions in a molten pool
|
Cheng, Songbai
|
|
2015
|
75 |
C |
p. 20-25
|
artikel
|
| 85 |
The Laputa code for lattice physics analyses
|
She, Ding
|
|
2015
|
75 |
C |
p. 303-308
|
artikel
|
| 86 |
The time dependence of the extinction probability with delayed neutrons
|
Williams, M.M.R.
|
|
2015
|
75 |
C |
p. 107-115
|
artikel
|
| 87 |
Transient performance analysis of pressurized safety injection tank with a partition
|
Bae, Youngmin
|
|
2015
|
75 |
C |
p. 232-238
|
artikel
|
| 88 |
Transient thermal–hydraulic analysis of complete single channel blockage accident of generic 10MW research reactor
|
Son, Hyung Min
|
|
2015
|
75 |
C |
p. 44-53
|
artikel
|
| 89 |
Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training Reactor
|
Alhassan, E.
|
|
2015
|
75 |
C |
p. 26-37
|
artikel
|
| 90 |
Using high temperature gas-cooled reactors for greenhouse gas reduction and energy neutral production of phosphate fertilizers
|
Haneklaus, Nils
|
|
2015
|
75 |
C |
p. 275-282
|
artikel
|
| 91 |
Verification of SAMG entry condition for APR1400
|
Yun, Junghyun
|
|
2015
|
75 |
C |
p. 404-412
|
artikel
|
| 92 |
Whole-core transport solution via deterministic SN transport/p-CMFD overlapping local/global calculation in hexagonal geometry problem
|
Yoo, Han Jong
|
|
2015
|
75 |
C |
p. 468-475
|
artikel
|
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