| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A combined immersed body and adaptive mesh method for simulating neutron transport within complex structures
|
Buchan, A.G.
|
|
2019
|
134 |
C |
p. 88-100
|
artikel
|
| 2 |
A comparison of transport methods for the solution of a problem with shadowing effects in spherical geometry
|
Vieira, W.J.
|
|
2019
|
134 |
C |
p. 370-375
|
artikel
|
| 3 |
A local fission matrix correction method for heterogeneous whole core transport with RAPID
|
He, Donghao
|
|
2019
|
134 |
C |
p. 263-272
|
artikel
|
| 4 |
Analysis of a control rod ejection accident in a boron-free small modular reactor with coupled neutronics/thermal-hydraulics code
|
Alzaben, Y.
|
|
2019
|
134 |
C |
p. 114-124
|
artikel
|
| 5 |
Analysis of the stochastic point reactor using Wiener-Hermite expansion
|
El-Beltagy, Mohamed
|
|
2019
|
134 |
C |
p. 250-257
|
artikel
|
| 6 |
Boiling water cooled travelling wave reactor
|
Chen, X.-N.
|
|
2019
|
134 |
C |
p. 342-349
|
artikel
|
| 7 |
Bubble-induced enhancement of single-phase liquid forced convection heat transfer during subcooled nucleate flow boiling
|
Amidu, Muritala Alade
|
|
2019
|
134 |
C |
p. 60-66
|
artikel
|
| 8 |
Closed loop configuration in the axial flux tilt control of a PWR
|
Zarei, M.
|
|
2019
|
134 |
C |
p. 47-53
|
artikel
|
| 9 |
Combined cycle-coupled high-temperature and very high-temperature gas-cooled reactors: Part I—Cycle optimization
|
Yang, Xiaoyong
|
|
2019
|
134 |
C |
p. 193-204
|
artikel
|
| 10 |
Comparison of deterministic and stochastic methods for external gamma dose rate calculation in the decommissioning of nuclear power plants
|
Bednár, Dávid
|
|
2019
|
134 |
C |
p. 67-76
|
artikel
|
| 11 |
Computational study of full-scale VHTR lower plenum for turbulent mixing assessment
|
Clifford, Corey E.
|
|
2019
|
134 |
C |
p. 101-113
|
artikel
|
| 12 |
Control and thermal analysis for SCWR startup
|
Yuan, Yuan
|
|
2019
|
134 |
C |
p. 27-37
|
artikel
|
| 13 |
Convergence study of variants of CMFD acceleration schemes for fixed source neutron transport problems in 2D Cartesian geometry with Fourier analysis
|
Chan, Yimeng
|
|
2019
|
134 |
C |
p. 273-283
|
artikel
|
| 14 |
Covariance-oriented sample transformation: A new sampling method for reactor-physics uncertainty analysis
|
Sui, Zhuojie
|
|
2019
|
134 |
C |
p. 452-463
|
artikel
|
| 15 |
Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark
|
Vasiliev, A.
|
|
2019
|
134 |
C |
p. 235-243
|
artikel
|
| 16 |
Design simulation studies of pipe mounted boron concentration meter
|
Dighe, Priyamvada M.
|
|
2019
|
134 |
C |
p. 414-423
|
artikel
|
| 17 |
Development of the universe based geometry criticality search capability in RMC and analysis of NHR200-II reactor
|
Li, Zeguang
|
|
2019
|
134 |
C |
p. 401-413
|
artikel
|
| 18 |
1D thermal creep channel flow in the BGK approximation by adding and doubling
|
Ganapol, Barry D.
|
|
2019
|
134 |
C |
p. 441-451
|
artikel
|
| 19 |
Editorial Board
|
|
|
2019
|
134 |
C |
p. ii
|
artikel
|
| 20 |
Effects of neutron irradiation on elastic modulus of RPV steel
|
Li, Chengliang
|
|
2019
|
134 |
C |
p. 20-26
|
artikel
|
| 21 |
Establishing safety goals on radiation protection for a space reactor through a case assessment of a loss-of-coolant accident in the International Space Station
|
Wang, Jiaxin
|
|
2019
|
134 |
C |
p. 170-177
|
artikel
|
| 22 |
Evaluation of fuzzy based HS and GSA on reloading cycle length optimization of PWR nuclear power plant
|
Mahmoudi, S.M.
|
|
2019
|
134 |
C |
p. 1-10
|
artikel
|
| 23 |
Evaluation of recycle pathways for out-of-specification uranium microspheres from the internal gelation process
|
Hunt, R.D.
|
|
2019
|
134 |
C |
p. 54-59
|
artikel
|
| 24 |
Experimental study on air ingression and residence time of a small-scale decay tank for a research reactor
|
Ji, Dae-Yun
|
|
2019
|
134 |
C |
p. 134-143
|
artikel
|
| 25 |
Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements
|
Li, Linfeng
|
|
2019
|
134 |
C |
p. 284-298
|
artikel
|
| 26 |
Full core 3D simulation of the BEAVRS benchmark with OpenMOC
|
Gunow, Geoffrey
|
|
2019
|
134 |
C |
p. 299-304
|
artikel
|
| 27 |
GET-based time-dependent lattice homogenization using a global-local approach
|
Schwanke, Peter
|
|
2019
|
134 |
C |
p. 359-369
|
artikel
|
| 28 |
GPU accelerated lattice Boltzmann method in neutron kinetics problems II: Neutron transport calculation
|
Wang, Yahui
|
|
2019
|
134 |
C |
p. 305-317
|
artikel
|
| 29 |
Impact of the volume heat source on the RANS-based CFD analysis of Molten Salt Reactors
|
Fiorina, Carlo
|
|
2019
|
134 |
C |
p. 376-382
|
artikel
|
| 30 |
In-situ fabrication of dispersion nuclear fuel pellets with a core-shell structure
|
Song, Tong
|
|
2019
|
134 |
C |
p. 258-262
|
artikel
|
| 31 |
Metaheuristic optimization method for compact reactor radiation shielding design based on genetic algorithm
|
Chen, Zhenping
|
|
2019
|
134 |
C |
p. 318-329
|
artikel
|
| 32 |
Minor fault detection of thermocouple sensor in nuclear power plants using time series analysis
|
Mandal, Shyamapada
|
|
2019
|
134 |
C |
p. 383-389
|
artikel
|
| 33 |
Modeling of flow blockage due to swell and rupture for analysis of LBLOCA using a multiple fuel rods scheme under high burnup condition
|
Bang, Young Seok
|
|
2019
|
134 |
C |
p. 350-358
|
artikel
|
| 34 |
Modeling the consequences of fuel assembly bowing on PWR core neutronics using a Monte-Carlo code
|
de Lambert, Stanislas
|
|
2019
|
134 |
C |
p. 330-341
|
artikel
|
| 35 |
Nuclear data and applications at the nuclear safety and radioprotection institute: Analysis, evaluation and application
|
Leal, L.
|
|
2019
|
134 |
C |
p. 244-249
|
artikel
|
| 36 |
Parameters influencing the activation of dismantling nuclear facility structures
|
Le Loirec, C.
|
|
2019
|
134 |
C |
p. 158-169
|
artikel
|
| 37 |
Prediction of temperature distribution in annular fuels using orthogonal collocation method
|
Esmaili, H.
|
|
2019
|
134 |
C |
p. 77-87
|
artikel
|
| 38 |
Quantification of system uncertainties in activation experiments at nuclear research reactors
|
MacConnachie, Elizabeth Laurel
|
|
2019
|
134 |
C |
p. 432-440
|
artikel
|
| 39 |
Reduced-order modeling of parameterized multi-group diffusion k-eigenvalue problems
|
German, Péter
|
|
2019
|
134 |
C |
p. 144-157
|
artikel
|
| 40 |
Sensor fault detection in nuclear power plants using symbolic dynamic filter
|
Mandal, Shyamapada
|
|
2019
|
134 |
C |
p. 390-400
|
artikel
|
| 41 |
SiC coating on HTR graphite spheres prepared by fluidized-bed chemical vapor deposition
|
Yang, Hui
|
|
2019
|
134 |
C |
p. 11-19
|
artikel
|
| 42 |
Solution of 3D linearly anisotropic scattering, fixed-source multigroup xyz reactor problems by the A N Boundary Element – Response Matrix method
|
Giusti, V.
|
|
2019
|
134 |
C |
p. 205-225
|
artikel
|
| 43 |
Solution of the neutron survival probability equation using k-eigenmode expansion
|
O’Rourke, Patrick F.
|
|
2019
|
134 |
C |
p. 178-192
|
artikel
|
| 44 |
Structural integrity assessment of secondary support structure and reactor pressure vessel following drop impact of core barrel assembly
|
Li, Yanhui
|
|
2019
|
134 |
C |
p. 38-46
|
artikel
|
| 45 |
SuperMC cloud for nuclear design and safety evaluation
|
Hu, Liqin
|
|
2019
|
134 |
C |
p. 424-431
|
artikel
|
| 46 |
The adjoint problem as physical heuristic for loading pattern optimization
|
Tal, O.
|
|
2019
|
134 |
C |
p. 226-234
|
artikel
|
| 47 |
The transport and decay of radioactive aerosols in a wall-bounded turbulent flow
|
Gu, Weiguo
|
|
2019
|
134 |
C |
p. 125-133
|
artikel
|
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