| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of the configurations and heat transfer of corium pool in RPV lower plenum
|
Liu, Lili
|
|
2019
|
124 |
C |
p. 172-178
|
artikel
|
| 2 |
Analysis of the impacts of homogeneous minor actinides loading in low void effect sodium fast reactor cores
|
Kooyman, T.
|
|
2019
|
124 |
C |
p. 572-578
|
artikel
|
| 3 |
Analysis of the inherent response of nuclear spent fuel pools
|
de la Rosa Blul, J.C.
|
|
2019
|
124 |
C |
p. 295-326
|
artikel
|
| 4 |
An experimental study on debris bed formation behavior at bottom-heated boiling condition
|
Cheng, Songbai
|
|
2019
|
124 |
C |
p. 150-163
|
artikel
|
| 5 |
A numerical simulation of single bubble growth in subcooled boiling water
|
Cheng, Ning
|
|
2019
|
124 |
C |
p. 179-186
|
artikel
|
| 6 |
Application of the SPH method to account for the angular dependence of multigroup resonant cross sections in thermal reactor calculations
|
Mao, Li
|
|
2019
|
124 |
C |
p. 98-118
|
artikel
|
| 7 |
Assessment of RANS models for flow in a loosely spaced bare rod bundle with heat transfer in low Prandtl number fluid
|
Mikuž, B.
|
|
2019
|
124 |
C |
p. 441-459
|
artikel
|
| 8 |
Assessment of the 153Eu and 154Eu neutron capture cross sections from the integral data assimilation of used nuclear fuel experiments
|
Rizzo, Axel
|
|
2019
|
124 |
C |
p. 524-532
|
artikel
|
| 9 |
Assessment of the potential for criticality in the far field of a used nuclear fuel repository
|
Atz, Milos
|
|
2019
|
124 |
C |
p. 28-38
|
artikel
|
| 10 |
Built-in capacitance sensor for control rod position measurement in NHR-200 with PEEK material
|
Hu, Guang
|
|
2019
|
124 |
C |
p. 372-384
|
artikel
|
| 11 |
CANDU-6 operation simulations using accident tolerant cladding candidates
|
Naceur, A.
|
|
2019
|
124 |
C |
p. 472-489
|
artikel
|
| 12 |
Comparative analysis of VERA depletion benchmark through consistent code-to-code comparison
|
Park, Jinsu
|
|
2019
|
124 |
C |
p. 385-398
|
artikel
|
| 13 |
Comparison of theoretical formulae and bootstrap method for statistical error estimation of Feynman-α method
|
Endo, Tomohiro
|
|
2019
|
124 |
C |
p. 606-615
|
artikel
|
| 14 |
Detached eddy simulation of turbulent and thermal mixing in a T-junction
|
Kang, Dong Gu
|
|
2019
|
124 |
C |
p. 245-256
|
artikel
|
| 15 |
Development and verification of a model for generation of MSFR few-group homogenized cross-sections based on a Monte Carlo code OpenMC
|
Zhuang, Kun
|
|
2019
|
124 |
C |
p. 187-197
|
artikel
|
| 16 |
Development and verification of a phase-field model for the equilibrium thermodynamics of U-Pu-Zr
|
Hirschhorn, Jacob
|
|
2019
|
124 |
C |
p. 490-502
|
artikel
|
| 17 |
Development of a Molten Salt Reactor specific depletion code MODEC
|
Xia, Shaopeng
|
|
2019
|
124 |
C |
p. 88-97
|
artikel
|
| 18 |
Editorial Board
|
|
|
2019
|
124 |
C |
p. ii
|
artikel
|
| 19 |
Evaluation of efficient cementation of fission 99Mo production process waste and feasibility disposal of cement waste form
|
Shon, Jong Sik
|
|
2019
|
124 |
C |
p. 342-348
|
artikel
|
| 20 |
Evaluation of neutronic safety parameters of the BAEC TRIGA Research Reactor with Wet Central Tube
|
Rahman, Md. Saifur
|
|
2019
|
124 |
C |
p. 533-540
|
artikel
|
| 21 |
Experimental investigations on out-of-pile single rod test using fuel simulator and assessment of FRAPTRAN 2.0 ballooning model
|
Yadav, Ashwini Kumar
|
|
2019
|
124 |
C |
p. 234-244
|
artikel
|
| 22 |
Experimental study and optimized design on electromagnetic pump for liquid sodium
|
Wang, Liu
|
|
2019
|
124 |
C |
p. 426-440
|
artikel
|
| 23 |
Framework and data management of digital design system for nuclear power
|
Shentu, Jun
|
|
2019
|
124 |
C |
p. 418-425
|
artikel
|
| 24 |
Genetic programming applied to the identification of accidents of a PWR nuclear power plant
|
Pinheiro, Victor Henrique Cabral
|
|
2019
|
124 |
C |
p. 335-341
|
artikel
|
| 25 |
Inverse estimation methods of unknown radioactive source for fuel debris search
|
Sugaya, Shinji
|
|
2019
|
124 |
C |
p. 49-57
|
artikel
|
| 26 |
Investigation of the reactor heat transfer function between the cold and the hot leg of the primary circuit
|
Kiss, Sándor
|
|
2019
|
124 |
C |
p. 327-334
|
artikel
|
| 27 |
Investigation on the critical heat flux in a 2 by 2 fuel assembly under low flow rate and high pressure with a CFD methodology
|
Zhang, Rui
|
|
2019
|
124 |
C |
p. 69-79
|
artikel
|
| 28 |
Modeling upgrade of probabilistically significant SBO scenarios with uncertainty analysis for the evaluation of system power uprate of limited scope
|
Du, Y.
|
|
2019
|
124 |
C |
p. 513-523
|
artikel
|
| 29 |
Multi-objective optimization of control parameters for a pressurized water reactor pressurizer using a genetic algorithm
|
Wang, Pengfei
|
|
2019
|
124 |
C |
p. 9-20
|
artikel
|
| 30 |
Narrowing transient testing pulse widths to enhance LWR RIA experiment design in the TREAT facility
|
Bess, John D.
|
|
2019
|
124 |
C |
p. 548-571
|
artikel
|
| 31 |
Novel fuzzy logic based coordinated control for multi-unit small modular reactor
|
Zhang, Bowen
|
|
2019
|
124 |
C |
p. 211-222
|
artikel
|
| 32 |
Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT
|
Bess, John D.
|
|
2019
|
124 |
C |
p. 270-294
|
artikel
|
| 33 |
Numerical investigation of the performance of moisture separators based on two-way coupling model by Lagrangian-Eulerian methodology
|
He, Xiaoqiang
|
|
2019
|
124 |
C |
p. 407-417
|
artikel
|
| 34 |
Numerical study of pebble recirculation in a two-dimensional pebble bed of stationary atmosphere using LB-IB-DEM coupled method
|
Gui, Nan
|
|
2019
|
124 |
C |
p. 58-68
|
artikel
|
| 35 |
On the EU-Japan roadmap for experimental research on corium behavior
|
Bechta, Sevostian
|
|
2019
|
124 |
C |
p. 541-547
|
artikel
|
| 36 |
On the number of tubes required to study oscillating vortices and frequency spectrums of tube arrays in cross flow
|
Tang, Di
|
|
2019
|
124 |
C |
p. 198-210
|
artikel
|
| 37 |
Phenomena identification and ranking table study for thermal hydraulics for Advanced High Temperature Reactor
|
Lin, Hsun-Chia
|
|
2019
|
124 |
C |
p. 257-269
|
artikel
|
| 38 |
Physics characteristics of internally cooled annular fuel for potential application in pressure tube heavy water reactors
|
Bromley, B.P.
|
|
2019
|
124 |
C |
p. 399-406
|
artikel
|
| 39 |
Predictive BWR core stability using feedback reactivity coefficients projected on neutronic eigenmodes
|
Dykin, Victor
|
|
2019
|
124 |
C |
p. 1-8
|
artikel
|
| 40 |
PWR advanced fuel high burnup-dependent xenon oscillation controllability assessment
|
Chang, G.S.
|
|
2019
|
124 |
C |
p. 592-605
|
artikel
|
| 41 |
Radial distributions of power and isotopic concentrations in candidate accident tolerant fuel U3Si2 and UO2/U3Si2 fuel pins with FeCrAl cladding
|
Chen, Shengli
|
|
2019
|
124 |
C |
p. 460-471
|
artikel
|
| 42 |
Research on the application of burnable poison ZrB2 and Gd2O3 in a small modular lead-based thermal reactor
|
Sun, Yanting
|
|
2019
|
124 |
C |
p. 21-27
|
artikel
|
| 43 |
Review on models to evaluate coolant activity under fuel defect condition in PWR
|
Dong, Bing
|
|
2019
|
124 |
C |
p. 223-233
|
artikel
|
| 44 |
Simulation of pressure waves propagation following LOCA in piping systems using Laplace Transform Finite Volume
|
Mahmoodi, R.
|
|
2019
|
124 |
C |
p. 164-171
|
artikel
|
| 45 |
SOPHIA: Development of Lagrangian-based CFD code for nuclear thermal-hydraulics and safety applications
|
Jo, Young Beom
|
|
2019
|
124 |
C |
p. 132-149
|
artikel
|
| 46 |
Study on neutronics of VVER-1200 with accident tolerant fuel cladding
|
Fejt, F.
|
|
2019
|
124 |
C |
p. 579-591
|
artikel
|
| 47 |
The MOCP code: method of characteristics code for pebble-bed HTR
|
Guo, Jian
|
|
2019
|
124 |
C |
p. 503-512
|
artikel
|
| 48 |
The path for innovative severe accident neutronics studies in ZPRs – Analysis of SNEAK-12B experiments for core disruption in LMFBRs
|
Margulis, Marat
|
|
2019
|
124 |
C |
p. 119-131
|
artikel
|
| 49 |
The research on coherent structure in 7-rod bundle lattice
|
Xiao, Hongguang
|
|
2019
|
124 |
C |
p. 39-48
|
artikel
|
| 50 |
Uncertainty quantification on advanced fuel cycle scenario simulations applying local and global methods
|
Skarbeli, A.V.
|
|
2019
|
124 |
C |
p. 349-356
|
artikel
|
| 51 |
Verification and validation of radiation source term capabilities in STREAM
|
Ebiwonjumi, Bamidele
|
|
2019
|
124 |
C |
p. 80-87
|
artikel
|
| 52 |
Verification of iterative matrix solutions for multipoint kinetics equations
|
Tommasi, Jean
|
|
2019
|
124 |
C |
p. 357-371
|
artikel
|
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