| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A general presentation of the SPH equivalence technique in non-fundamental mode cases
|
Hébert, Alain
|
|
|
141 |
C |
p.
|
artikel
|
| 2 |
A multi-scale CFD-system coupled code for transient analysis of the passive residual heat removal system of MHTGR
|
Zhao, Hangbin
|
|
|
141 |
C |
p.
|
artikel
|
| 3 |
Analysis of thermal stratification phenomena in the CIRCE-HERO facility
|
Buzzi, F.
|
|
|
141 |
C |
p.
|
artikel
|
| 4 |
Analytical and numerical solutions of sodium particle ignition based on the thermal explosion theory with different forms of reaction rates and variable thermal conductivity
|
EL-Sayed, Saad A.
|
|
|
141 |
C |
p.
|
artikel
|
| 5 |
An Arbitrary Lagrangian-Eulerian, coupled neutronics-shock physics model for the analysis of shockwave implosion of solid fissile materials
|
Cervi, E.
|
|
|
141 |
C |
p.
|
artikel
|
| 6 |
An efficient method for passive safety systems reliability assessment
|
Yu, Yu
|
|
|
141 |
C |
p.
|
artikel
|
| 7 |
A new approach for fault diagnosis with full-scope simulator based on state information imaging in nuclear power plant
|
Yao, Yuantao
|
|
|
141 |
C |
p.
|
artikel
|
| 8 |
A new Monte Carlo approach for solution of the time dependent neutron transport equation based on nodal discretization to simulate the xenon oscillation with feedback
|
Ghaderi Mazaher, Meysam
|
|
|
141 |
C |
p.
|
artikel
|
| 9 |
An inverse-distance-based fitting term for 3D-Var data assimilation in nuclear core simulation
|
Gong, Helin
|
|
|
141 |
C |
p.
|
artikel
|
| 10 |
A nonintrusive adaptive reduced order modeling approach for a molten salt reactor system
|
Alsayyari, Fahad
|
|
|
141 |
C |
p.
|
artikel
|
| 11 |
A simple implicit coupling scheme for Monte Carlo neutronics and isotopic depletion
|
Cosgrove, P.
|
|
|
141 |
C |
p.
|
artikel
|
| 12 |
Assembly design of a fluoride salt-cooled high temperature commercial-scale reactor: Neutronics evaluation and parametric analysis
|
Krishna, Vitesh
|
|
|
141 |
C |
p.
|
artikel
|
| 13 |
Automated critical power limit estimation for natural convection-cooled research reactor core
|
Son, Hyung Min
|
|
|
141 |
C |
p.
|
artikel
|
| 14 |
Burnup analysis of the pebble-bed fluoride-salt-cooled high-temperature reactor based on the Chord Length Sampling method
|
Li, Zhifeng
|
|
|
141 |
C |
p.
|
artikel
|
| 15 |
Canister spacing in high-level radioactive nuclear waste repository
|
Zhou, Xiang-yun
|
|
|
141 |
C |
p.
|
artikel
|
| 16 |
CFD investigation for a 7-pin wire-wrapped fuel assembly with different shapes of fuel duct wall
|
Zhao, Yuanyuan
|
|
|
141 |
C |
p.
|
artikel
|
| 17 |
Challenges and sensitivities in the modelling of Fukushima Daiichi Unit 1 unfolding with MELCOR 2.2
|
Herranz, Luis E.
|
|
|
141 |
C |
p.
|
artikel
|
| 18 |
Clearance measurement for general steel waste
|
Yokoyama, Kaoru
|
|
|
141 |
C |
p.
|
artikel
|
| 19 |
Code improvement, separate-effect validation, and benchmark calculation for thermal-hydraulic analysis of helical coil once-through steam generator
|
Lian, Qiang
|
|
|
141 |
C |
p.
|
artikel
|
| 20 |
Comparison of research reactor full-core diffusion calculations with few-group cross sections generated using Serpent and MCU-PTR
|
Shchurovskaya, M.V.
|
|
|
141 |
C |
p.
|
artikel
|
| 21 |
Coupled Monte Carlo-CFD analysis of heat transfer phenomena in a supercritical water reactor fuel assembly
|
Castro, Landy
|
|
|
141 |
C |
p.
|
artikel
|
| 22 |
Develop CATE V3.0 code for multi-phase ACPs analysis in a typical PWR
|
Guo, Qingyang
|
|
|
141 |
C |
p.
|
artikel
|
| 23 |
Development of a user-friendly interface IRONS for atmospheric dispersion database for nuclear emergency preparedness based on the Fukushima database
|
El-Asaad, Hamza
|
|
|
141 |
C |
p.
|
artikel
|
| 24 |
Distributed-parallel CFD computation for all fuel assemblies in PWR core
|
Chen, Guangliang
|
|
|
141 |
C |
p.
|
artikel
|
| 25 |
Editorial Board
|
|
|
|
141 |
C |
p.
|
artikel
|
| 26 |
Efficient uncertainty quantification for PWR during LOCA using unscented transform with singular value decomposition
|
Foad, Basma
|
|
|
141 |
C |
p.
|
artikel
|
| 27 |
Enhancing Tehran research reactor safety using a core differential pressure measuring system
|
Abedi, Ebrahim
|
|
|
141 |
C |
p.
|
artikel
|
| 28 |
Experimental study on the separation performance of a full-scale SG steam-water separator
|
Liu, Li
|
|
|
141 |
C |
p.
|
artikel
|
| 29 |
Experiments on helium breakdown at high pressure and temperature in uniform field and its simulation using COMSOL Multiphysics and FD-FCT
|
You, Qi
|
|
|
141 |
C |
p.
|
artikel
|
| 30 |
High temperature ultra-small modular reactor: Pre-conceptual design
|
Kaffezakis, Naiki
|
|
|
141 |
C |
p.
|
artikel
|
| 31 |
Impact of initial MCNP spectrum guess on experiment-based neutron spectrum determination at Missouri S&T reactor
|
ALQahtani, Meshari
|
|
|
141 |
C |
p.
|
artikel
|
| 32 |
Investigating the Performance and safety features of Pressurized water reactors using the burnable poisons
|
Reda, Sonia M.
|
|
|
141 |
C |
p.
|
artikel
|
| 33 |
Investigation on corium spreading over ceramic and concrete substrates in VULCANO VE-U7 experiment with moving particle semi-implicit method
|
Jubaidah,
|
|
|
141 |
C |
p.
|
artikel
|
| 34 |
Investigation on effects of Fluid-Structure-Interaction (FSI) on the lubrication performances of water lubricated bearing in primary circuit loop system of nuclear power plant
|
Xie, Zhongliang
|
|
|
141 |
C |
p.
|
artikel
|
| 35 |
MCBMPI-A parallel Monte Carlo burnup code based on message passing interface
|
Yang, Wankui
|
|
|
141 |
C |
p.
|
artikel
|
| 36 |
Measurement method for deformation and contact force of the fuel assembly for China fast reactor under thermal gradient
|
Wang, Kaiqiang
|
|
|
141 |
C |
p.
|
artikel
|
| 37 |
Measurements of the impact of carbon monoxide on the performance of passive autocatalytic recombiners at containment-typical conditions in the THAI facility
|
Freitag, M.
|
|
|
141 |
C |
p.
|
artikel
|
| 38 |
Monte Carlo neutron-kinetics analysis in continuous time and energy
|
Li, Jie
|
|
|
141 |
C |
p.
|
artikel
|
| 39 |
Multi-scale coupling of CFD code and sub-channel code based on a generic coupling architecture
|
Zhang, Xilin
|
|
|
141 |
C |
p.
|
artikel
|
| 40 |
Neutron transport criticality calculations using a parallel monolithic multilevel Schwarz preconditioner together with a nonlinear diffusion acceleration method
|
Kong, Fande
|
|
|
141 |
C |
p.
|
artikel
|
| 41 |
New semi-analytical algorithm for solving PKEs based on Euler-Maclaurin approximation
|
Xiao, Yunlong
|
|
|
141 |
C |
p.
|
artikel
|
| 42 |
Novel design integration for advanced nuclear heat-pipe systems
|
Mueller, Cole
|
|
|
141 |
C |
p.
|
artikel
|
| 43 |
Nuclide inventory of FIR1 TRIGA research reactor fuel
|
Räty, Antti
|
|
|
141 |
C |
p.
|
artikel
|
| 44 |
Numerical approach for estimating the conditions for natural circulation in a simple nuclear passive system
|
Olatubosun, Samuel Abiodun
|
|
|
141 |
C |
p.
|
artikel
|
| 45 |
Proliferation resistance evaluation of an HTGR transuranic fuel cycle using PRAETOR code
|
Aoki, Takeshi
|
|
|
141 |
C |
p.
|
artikel
|
| 46 |
Reactivity Initiated Accident transient testing on irradiated fuel rods in PWR conditions: The CABRI International Program
|
Biard, Bruno
|
|
|
141 |
C |
p.
|
artikel
|
| 47 |
Research on hydrogen risk and hydrogen control system in marine nuclear reactor
|
Lyu, Xuefeng
|
|
|
141 |
C |
p.
|
artikel
|
| 48 |
Research on reflux phenomenon of liquid film on the wall of corrugated plate dryer
|
Wang, Bo
|
|
|
141 |
C |
p.
|
artikel
|
| 49 |
Rod drop transient at VR-1 reactor – Experiment and Serpent transient calculation analysis
|
Novak, Ondrej
|
|
|
141 |
C |
p.
|
artikel
|
| 50 |
Singular value decomposition of adjoint flux distributions for Monte Carlo variance reduction
|
Biondo, Elliott D.
|
|
|
141 |
C |
p.
|
artikel
|
| 51 |
State estimation of external neutron source driven sub-critical core using adaptive Kalman filter
|
Li, Wenhuai
|
|
|
141 |
C |
p.
|
artikel
|
| 52 |
Study of the radiolytic decomposition of CsI and CdI2 aerosols deposited on stainless steel, quartz and Epoxy painted surfaces
|
Bosland, Loïc
|
|
|
141 |
C |
p.
|
artikel
|
| 53 |
The study for activation evaluation on activated structures in nuclear power plant with 40 years operation history
|
Dong Sohn, Hee
|
|
|
141 |
C |
p.
|
artikel
|
| 54 |
Transient analysis of tritium transport characteristics of thorium molten salt reactor with solid fuel
|
Wang, Chenglong
|
|
|
141 |
C |
p.
|
artikel
|
| 55 |
Uncertainties propagation in the UAM numerical rod ejection benchmark
|
Sargeni, A.
|
|
|
141 |
C |
p.
|
artikel
|
| 56 |
Uncertainty quantification of in-pool fission product retention during BWR station BlackOut sequences
|
Herranz, Luis E.
|
|
|
141 |
C |
p.
|
artikel
|
| 57 |
Validation with the MARS and TASS/SMR codes based on experimental results of a pressurizer safety valve line break at the SMART-ITL facility
|
Chung, Young-jong
|
|
|
141 |
C |
p.
|
artikel
|
| 58 |
Wall temperature prediction at critical heat flux using a machine learning model
|
Park, Hae Min
|
|
|
141 |
C |
p.
|
artikel
|
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