| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A CFD/CSD coupled method with high order and its applications in flow induced vibrations of tube arrays in cross flow
|
Tang, Di
|
|
2019
|
130 |
C |
p. 347-356
|
artikel
|
| 2 |
A modal ACMFD formulation of the HEXNEM3 method for solving the time-dependent neutron diffusion equation
|
Kolev, Srebrin
|
|
2019
|
130 |
C |
p. 331-337
|
artikel
|
| 3 |
An advanced numerical framework for the simulation of flow induced vibration for nuclear applications
|
De Santis, Dante
|
|
2019
|
130 |
C |
p. 218-231
|
artikel
|
| 4 |
Analysis of start-up and long-term operation characteristics of passive residual heat removal system
|
Lyu, Xing
|
|
2019
|
130 |
C |
p. 69-81
|
artikel
|
| 5 |
An integrated framework for analysing operational events in China nuclear power plants
|
Zou, Yanhua
|
|
2019
|
130 |
C |
p. 192-199
|
artikel
|
| 6 |
Axial helium compressor for high-temperature gas-cooled reactor: A review
|
Tian, Zhitao
|
|
2019
|
130 |
C |
p. 54-68
|
artikel
|
| 7 |
Characteristics of the high-temperature water film evaporation with countercurrent turbulent air flow in the duct
|
Li, Cheng
|
|
2019
|
130 |
C |
p. 1-7
|
artikel
|
| 8 |
Comparison of sensitivity calculation between mathematical and physical adjoint in the 2-D/1-D transport solver KYADJ
|
Wu, Qu
|
|
2019
|
130 |
C |
p. 357-364
|
artikel
|
| 9 |
Correlation diagnosis method for heterogeneous Monte Carlo eigenvalue simulations based on a diffusion approximation
|
Miao, Jilang
|
|
2019
|
130 |
C |
p. 301-318
|
artikel
|
| 10 |
Corrigendum to ‘Uncertainty quantification of sodium-cooled fast reactor based on the UAM-SFR benchmarks: From pin-cell to full core’ [Ann. Nuclear Energy 128 (2019), 433–442]
|
Qiao, Liang
|
|
2019
|
130 |
C |
p. 518
|
artikel
|
| 11 |
Cross-section-induced uncertainty evaluation of MA sample irradiation test calculations with consideration of dosimeter data
|
Sugino, Kazuteru
|
|
2019
|
130 |
C |
p. 118-123
|
artikel
|
| 12 |
Deflection predictions of involute-shaped fuel plates using a fully-coupled numerical approach
|
Curtis, Franklin G.
|
|
2019
|
130 |
C |
p. 184-191
|
artikel
|
| 13 |
Determination of 137Cs content in fuel assemblies of a zero power reactor by Monte Carlo based efficiency calibration
|
Radócz, G.
|
|
2019
|
130 |
C |
p. 512-517
|
artikel
|
| 14 |
Development and validation of boron diffusion model in nuclear reactor core subchannel analysis
|
Yu, Hao
|
|
2019
|
130 |
C |
p. 208-217
|
artikel
|
| 15 |
Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materials
|
Kim, Mi Jin
|
|
2019
|
130 |
C |
p. 107-117
|
artikel
|
| 16 |
Editorial Board
|
|
|
2019
|
130 |
C |
p. ii
|
artikel
|
| 17 |
Error analysis of approximations and treatments commonly made in multi-group library and self-shielding calculation based on NECP-X
|
He, Qingming
|
|
2019
|
130 |
C |
p. 418-430
|
artikel
|
| 18 |
Estimation of some neutron physics characteristics by Monte-Carlo method using the importance function
|
Gurevich, M.I.
|
|
2019
|
130 |
C |
p. 388-393
|
artikel
|
| 19 |
Evaluation of FRAPCON-4.0’s uncertainties predicting PCMI during power ramps
|
Feria, F.
|
|
2019
|
130 |
C |
p. 411-417
|
artikel
|
| 20 |
Experimental investigation of the turbulent flow in a rod bundle channel with spacer grids
|
Qi, Peiyao
|
|
2019
|
130 |
C |
p. 142-156
|
artikel
|
| 21 |
Experimental studies on bubble breakup mechanism in a venturi bubble generator
|
Song, Yuchen
|
|
2019
|
130 |
C |
p. 259-270
|
artikel
|
| 22 |
Experimental studies on morphological properties of sodium combustion, fission product, structural material and mixed aerosols in a closed chamber towards fast reactor safety
|
Pujala, Usha
|
|
2019
|
130 |
C |
p. 319-330
|
artikel
|
| 23 |
Fuel management code system against experimental measurements of the CMRR reactor
|
Wang, Guanbo
|
|
2019
|
130 |
C |
p. 124-130
|
artikel
|
| 24 |
Hybrid Monte Carlo-deterministic method for 3D neutron transport simulation based on energy region division
|
Zhuang, Sixuan
|
|
2019
|
130 |
C |
p. 271-276
|
artikel
|
| 25 |
Impact assessment of alternative back-end fuel cycles on geological disposal of resultant spent fuels and high level wastes
|
Bulut Acar, Banu
|
|
2019
|
130 |
C |
p. 452-472
|
artikel
|
| 26 |
Impact of shield elements on the WWER-440 reactor pressure vessel activation
|
Narkunas, Ernestas
|
|
2019
|
130 |
C |
p. 394-401
|
artikel
|
| 27 |
Implementation of a dynamic Monte Carlo method for transients analysis with thermal-hydraulic feedbacks using MCNPX code
|
Mazaher, Meysam Ghaderi
|
|
2019
|
130 |
C |
p. 240-249
|
artikel
|
| 28 |
Investigation on transient thermal hydraulics of reduced scale passive residual heat removal heat exchanger in tank
|
Tao, Jiaqi
|
|
2019
|
130 |
C |
p. 402-410
|
artikel
|
| 29 |
Methods of studying the effect of rough surfaces on reactivity in two-dimensional reactor physics problems
|
Williams, A.J.R.
|
|
2019
|
130 |
C |
p. 493-511
|
artikel
|
| 30 |
Modeling and evaluation of fissile material utilization of the UMLRR using Monte Carlo MCNP6 code
|
Dim, O.U.
|
|
2019
|
130 |
C |
p. 365-376
|
artikel
|
| 31 |
Natural circulation flow resistance correlations in a rod bundle channel under vertical, inclined and rolling motion conditions
|
Zhu, Zhiqiang
|
|
2019
|
130 |
C |
p. 173-183
|
artikel
|
| 32 |
Neutronic and thermal-hydraulic feasibility studies for High Flux Isotope Reactor conversion to low-enriched uranium silicide dispersion fuel
|
Chandler, D.
|
|
2019
|
130 |
C |
p. 277-292
|
artikel
|
| 33 |
Neutronic modeling of debris beds for a criticality evaluation
|
Freiría López, M.
|
|
2019
|
130 |
C |
p. 164-172
|
artikel
|
| 34 |
Numerical investigation on the CHF model and prediction for the external cooling channel of lower head
|
Dan, Li
|
|
2019
|
130 |
C |
p. 232-239
|
artikel
|
| 35 |
Numerical study of mixing pebble flow with different density in circulating packed bed
|
Wu, Mengqi
|
|
2019
|
130 |
C |
p. 483-492
|
artikel
|
| 36 |
Numerical study on the thermal stratification characteristics of AP1000 pressurizer surge line
|
Wang, Mingjun
|
|
2019
|
130 |
C |
p. 8-19
|
artikel
|
| 37 |
Off-design performance and power-control strategy for combined cycle coupled with high-temperature gas-cooled reactor
|
Qu, Xinhe
|
|
2019
|
130 |
C |
p. 338-346
|
artikel
|
| 38 |
Overall thermal-hydraulic behavior in an SBO test using HSIT in the ATLAS facility
|
Kim, Yeon-Sik
|
|
2019
|
130 |
C |
p. 250-258
|
artikel
|
| 39 |
Phenomenological study on the Ex-pin phenomena in the initial phase of HCDA on metal-fueled SFR using simulant
|
Lee, Min Ho
|
|
2019
|
130 |
C |
p. 34-46
|
artikel
|
| 40 |
Preliminary interpretative analysis of the QUENCH-18 bundle test using SCDAPSim/mod3.5
|
Birchley, Jonathan C.
|
|
2019
|
130 |
C |
p. 20-33
|
artikel
|
| 41 |
Reactor physics analysis of a new Accident Tolerant Fuel called Fuel-in-Fibers
|
Hiscox, Briana
|
|
2019
|
130 |
C |
p. 473-482
|
artikel
|
| 42 |
Reformulation of the coupled problem for the simplified closed channel
|
Tomatis, Daniele
|
|
2019
|
130 |
C |
p. 377-387
|
artikel
|
| 43 |
Reliability and loading-following studies of a heat pipe cooled, AMTEC conversion space reactor power system
|
Ge, Li
|
|
2019
|
130 |
C |
p. 82-92
|
artikel
|
| 44 |
Risk-informed approach for design optimization during low power and shutdown operation
|
Oh, Ji-Yong
|
|
2019
|
130 |
C |
p. 293-300
|
artikel
|
| 45 |
Sensitivity analysis of source intensity and time bin size for the Rossi-alpha method in a numerical reactor model
|
Kong, Chidong
|
|
2019
|
130 |
C |
p. 157-163
|
artikel
|
| 46 |
Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
|
Clifford, I.
|
|
2019
|
130 |
C |
p. 440-451
|
artikel
|
| 47 |
The computer aided cutting planning of components using genetic algorithms for decommissioning of a nuclear reactor
|
Tsai, Po-Chou
|
|
2019
|
130 |
C |
p. 200-207
|
artikel
|
| 48 |
The Laplace transform method for solving the burnup equation with external feed
|
Xia, Shaopeng
|
|
2019
|
130 |
C |
p. 47-53
|
artikel
|
| 49 |
The research on the heat transfer of a solid-core nuclear reactor cooled by heat pipe through a numerical simulation, considering the assembly gaps
|
Cao, Hanwen
|
|
2019
|
130 |
C |
p. 431-439
|
artikel
|
| 50 |
Thermal hydraulic investigation of heat transfer from a completely blocked fuel subassembly of SFR
|
Sarkar, Madhusree
|
|
2019
|
130 |
C |
p. 131-141
|
artikel
|
| 51 |
Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: Fission product release and transport analysis
|
Fernandez-Moguel, L.
|
|
2019
|
130 |
C |
p. 93-106
|
artikel
|
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