| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A criterion for the occurrence of large scale vortex structure in tight lattice bundle
|
Rui, Li
|
|
|
148 |
C |
p.
|
artikel
|
| 2 |
A diffusion synthetic acceleration approach to k-eigenvalue neutron transport using PJFNK
|
Prince, Zachary
|
|
|
148 |
C |
p.
|
artikel
|
| 3 |
A morphological image processing method for simultaneous scrutinization of particle position and velocity in pebble flow
|
Wang, Qian
|
|
|
148 |
C |
p.
|
artikel
|
| 4 |
Assessment of new severe accident mitigation systems on containment pressure of the WWER1000/V446
|
Gharari, R.
|
|
|
148 |
C |
p.
|
artikel
|
| 5 |
Back propagation (BP) neural network prediction and chaotic characteristics analysis of free falling liquid film fluctuation on corrugated plate wall
|
Wang, Bo
|
|
|
148 |
C |
p.
|
artikel
|
| 6 |
Development of RAPID transport calculation with heterogeneous temperature distribution
|
He, Donghao
|
|
|
148 |
C |
p.
|
artikel
|
| 7 |
Dynamic simulation of the CEFR control rod drop experiments with the Monte Carlo code Serpent
|
Fridman, Emil
|
|
|
148 |
C |
p.
|
artikel
|
| 8 |
Editorial Board
|
|
|
|
148 |
C |
p.
|
artikel
|
| 9 |
Experimental study on melt-jet behavior during SFR core disruptive accidents using simulant materials
|
Ye, Yiji
|
|
|
148 |
C |
p.
|
artikel
|
| 10 |
Finite difference Jacobian based Newton-Krylov coupling method for solving multi-physics nonlinear system of nuclear reactor
|
Liu, Baokun
|
|
|
148 |
C |
p.
|
artikel
|
| 11 |
Fission product release tests with uranium dioxide fuel and lead under conditions related to reactor accidents for lead-cooled reactors
|
Bell, J. Stuart
|
|
|
148 |
C |
p.
|
artikel
|
| 12 |
Flow behavior of liquid falling film on a horizontal corrugated tube
|
Zhang, Yishuo
|
|
|
148 |
C |
p.
|
artikel
|
| 13 |
Hazard analysis for identifying common cause failures of digital safety systems using a redundancy-guided systems-theoretic approach
|
Bao, Han
|
|
|
148 |
C |
p.
|
artikel
|
| 14 |
Implementation of Grey Wolf Optimization (GWO) algorithm to multi-objective loading pattern optimization of a PWR reactor
|
Naserbegi, A.
|
|
|
148 |
C |
p.
|
artikel
|
| 15 |
Improved PCA model for multiple fault detection, isolation and reconstruction of sensors in nuclear power plant
|
Yu, Yue
|
|
|
148 |
C |
p.
|
artikel
|
| 16 |
Improvement of PIE analysis with a full core simulation: The U1 case
|
Rochman, D.
|
|
|
148 |
C |
p.
|
artikel
|
| 17 |
Influence of the radial neutron reflector efficiency on the power of fast nuclear-burning-wave reactor
|
Fomin, S.P.
|
|
|
148 |
C |
p.
|
artikel
|
| 18 |
Initial development of an RIA envelope for dispersed nuclear fuel
|
Capps, Nathan
|
|
|
148 |
C |
p.
|
artikel
|
| 19 |
Investigate the possibility of burning weapon-grade plutonium using a concentric rods BS assembly of VVER-1200
|
Abdelghafar Galahom, A.
|
|
|
148 |
C |
p.
|
artikel
|
| 20 |
Investigation of the equalization capability of submerged perforated sheets under thermal–hydraulic conditions of a horizontal steam generator
|
Le, T.T.
|
|
|
148 |
C |
p.
|
artikel
|
| 21 |
MARS best-estimate evaluation using ATLAS test data on 8.5″ cold leg break LOCA
|
Kim, Yeon-Sik
|
|
|
148 |
C |
p.
|
artikel
|
| 22 |
MDO strategy for meridian plane design to improve energy conversion capability of LFR main coolant pump
|
Zhao, Yuanyuan
|
|
|
148 |
C |
p.
|
artikel
|
| 23 |
Measurement of core flow distribution in a research reactor using plate-type fuel assembly
|
Park, Jonghark
|
|
|
148 |
C |
p.
|
artikel
|
| 24 |
Measurements on (233U, Th)O2 fuel by substitution experiments in the ZED-2 critical facility
|
Adams, F.P.
|
|
|
148 |
C |
p.
|
artikel
|
| 25 |
Modeling and experimental validation of rotary riffling method for nuclear material input accountancy
|
Yoo, Tae-Sic
|
|
|
148 |
C |
p.
|
artikel
|
| 26 |
Modeling of the droplet entrainment rate in the post-dryout regime for the analysis of a reflood phase
|
Yoo, Jee Min
|
|
|
148 |
C |
p.
|
artikel
|
| 27 |
Neutronic simulation of China experimental fast reactor start-up tests- part II: MCS code Monte Carlo calculation
|
Quoc Tran, Tuan
|
|
|
148 |
C |
p.
|
artikel
|
| 28 |
New variants of Bennett variance method with correlation indices for reducing delayed-neutron contribution
|
Kitamura, Yasunori
|
|
|
148 |
C |
p.
|
artikel
|
| 29 |
Nonlinear stability analysis of a self-pressurized, natural circulation integral reactor via the Lyapunov's second method
|
Pilehvar, A.F.
|
|
|
148 |
C |
p.
|
artikel
|
| 30 |
Nuclear data uncertainties for core parameters based on Swiss BWR operated cycles
|
Rochman, D.
|
|
|
148 |
C |
p.
|
artikel
|
| 31 |
Numerical and experimental study on thermal-hydraulic behaviors in the secondary side of passive residual heat removal heat exchanger
|
Tao, Jiaqi
|
|
|
148 |
C |
p.
|
artikel
|
| 32 |
Numerical investigation of rod bundle thermal–hydraulic behavior during reflood transients using COBRA-TF
|
Jin, Yue
|
|
|
148 |
C |
p.
|
artikel
|
| 33 |
Nyström method applied to the transport equation in an axisymmetric cylinder
|
Bublitz, César
|
|
|
148 |
C |
p.
|
artikel
|
| 34 |
On the approximate solutions of the fractional neutron point kinetics equations
|
Sadeghi, H.
|
|
|
148 |
C |
p.
|
artikel
|
| 35 |
Optimal design of a VVER-1000 nuclear reactor core with dual cooled annular fuel based on the reactivity temperature coefficients using Thermal hydraulic and neutronic analysis by implementing the genetic algorithms
|
Kianpour, R.
|
|
|
148 |
C |
p.
|
artikel
|
| 36 |
Optimization of Swiss used nuclear fuel canister for final repository: Homogeneous vs. mixed loading
|
Rochman, D.
|
|
|
148 |
C |
p.
|
artikel
|
| 37 |
Performance of ENDF/B-VIII.0 library for VVER reactors criticality safety, fuel depletion and reactor dosimetry applications
|
Lovecký, M.
|
|
|
148 |
C |
p.
|
artikel
|
| 38 |
Quadratic axial expansion function with sub-plane acceleration scheme for the high-fidelity transport code PROTEUS-MOC
|
Zhang, Guangchun
|
|
|
148 |
C |
p.
|
artikel
|
| 39 |
Reactivity and power regulation in candle reactors
|
Khotyayintsev, Volodymyr M.
|
|
|
148 |
C |
p.
|
artikel
|
| 40 |
Semi-analytical methods for SP3 equations solver verification including third-order scattering anisotropy
|
Babcsány, Boglárka
|
|
|
148 |
C |
p.
|
artikel
|
| 41 |
Sensitivity and uncertainty analysis of a reduced-order model of nonlinear BWR dynamics: I. Forward sensitivity analysis
|
Di Rocco, Federico
|
|
|
148 |
C |
p.
|
artikel
|
| 42 |
Sensitivity and uncertainty analysis of a reduced-order model of nonlinear BWR dynamics: II adjoint sensitivity analysis
|
Gabriel Cacuci, Dan
|
|
|
148 |
C |
p.
|
artikel
|
| 43 |
Sensitivity and uncertainty analysis of a reduced-order model of nonlinear BWR dynamics. III: Uncertainty analysis results
|
Di Rocco, Federico
|
|
|
148 |
C |
p.
|
artikel
|
| 44 |
Separation of noble gases through nano porous material membranes
|
Assfour, B.
|
|
|
148 |
C |
p.
|
artikel
|
| 45 |
Strategies for thorium fuel cycle transition in the SD-TMSR
|
Ashraf, O.
|
|
|
148 |
C |
p.
|
artikel
|
| 46 |
Study of a fine-mesh 1:1 Computational Fluid Dynamics – Monte Carlo neutron transport coupling method with discretization uncertainty estimation
|
Vieira, Tiago Augusto Santiago
|
|
|
148 |
C |
p.
|
artikel
|
| 47 |
Study of boron diffusion models and dilution accidents in nuclear reactor: A comprehensive review
|
Yu, Hao
|
|
|
148 |
C |
p.
|
artikel
|
| 48 |
Study of the material release during PHÉBUS FPT-1 bundle phase with MELCOR 2.2
|
Darnowski, Piotr
|
|
|
148 |
C |
p.
|
artikel
|
| 49 |
The cavitation performance analysis of the RCP under LBLOCA at inlet
|
An, Ce
|
|
|
148 |
C |
p.
|
artikel
|
| 50 |
The NUIT code for nuclide inventory calculations
|
Li, Jian
|
|
|
148 |
C |
p.
|
artikel
|
| 51 |
Thermal-and fast-spectrum molten salt reactors for minor actinides transmutation
|
Ashraf, O.
|
|
|
148 |
C |
p.
|
artikel
|
| 52 |
Verification and validation of MPS potential force interface tension model for stratification simulation
|
Zhu, Yingzi
|
|
|
148 |
C |
p.
|
artikel
|
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