| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comprehensive Bayesian framework for the development, validation and uncertainty quantification of thermal-hydraulic models
|
Cocci, Riccardo
|
|
|
172 |
C |
p.
|
artikel
|
| 2 |
A medium temperature heat pipe cooled reactor
|
Li, S.N.
|
|
|
172 |
C |
p.
|
artikel
|
| 3 |
A multiphysics model of the versatile test reactor based on the MOOSE framework
|
Martin, Nicolas
|
|
|
172 |
C |
p.
|
artikel
|
| 4 |
A new methodology for thermal analysis of geological disposal of spent nuclear fuel using integrated simulations of gamma heating and finite element modeling
|
Jansson, Peter
|
|
|
172 |
C |
p.
|
artikel
|
| 5 |
An optimized numerical method on corrosion in the non–isothermal lead–bismuth eutectic loops with solid–phase oxygen control system
|
Li, Xiaobo
|
|
|
172 |
C |
p.
|
artikel
|
| 6 |
Capturing multiphysics effects in hydride moderated microreactors using MARM
|
Mehta, Vedant K.
|
|
|
172 |
C |
p.
|
artikel
|
| 7 |
Development and verification of Geant4-based parallel computing Monte Carlo simulations for nuclear logging applications
|
Wang, Yang
|
|
|
172 |
C |
p.
|
artikel
|
| 8 |
Development of 3-D numerical methodology to investigate transient characteristics of fuel temperature and hydrated residual water during drying process of dry storage system
|
Tseng, Y.S.
|
|
|
172 |
C |
p.
|
artikel
|
| 9 |
Editorial Board
|
|
|
|
172 |
C |
p.
|
artikel
|
| 10 |
Effect of thermo-physical properties of accident tolerant fuels on transient fuel behaviors and the safety
|
He, Sihong
|
|
|
172 |
C |
p.
|
artikel
|
| 11 |
Entrance effect on submicron particles penetration through narrow paths
|
Wang, Shanpu
|
|
|
172 |
C |
p.
|
artikel
|
| 12 |
Evaluation of service reliability of AP1000 nuclear reactor coolant pump rotor-can
|
Cui, Yan
|
|
|
172 |
C |
p.
|
artikel
|
| 13 |
Evaluation of the canister spacing and criticality safety of spent plutonium-thorium nuclear fuel
|
Ibrahim, Remon
|
|
|
172 |
C |
p.
|
artikel
|
| 14 |
Experimental analysis of droplet impacting on inclined wall of the corrugated plate dryer in steam generator of nuclear power plants
|
Ru, Li
|
|
|
172 |
C |
p.
|
artikel
|
| 15 |
Experimental study and analysis on the interfacial drag of two-phase flow in porous media
|
Zhao, Haoxiang
|
|
|
172 |
C |
p.
|
artikel
|
| 16 |
Experimental study of heat distribution in a Non-uniform heat source of a natural circulation loop
|
Bello, Solomon
|
|
|
172 |
C |
p.
|
artikel
|
| 17 |
Experimental study on combustion characteristics of mixed sodium fire in a well-ventilated environment compared with confined space
|
Ma, Yao-long
|
|
|
172 |
C |
p.
|
artikel
|
| 18 |
Exponential fitting of PWR decay heat data at short cooling time for use in the PRESTO experiment
|
Muratori, Francesco
|
|
|
172 |
C |
p.
|
artikel
|
| 19 |
Fluid-structure coupled vibration characteristics of liquid immersed square channels within confinement
|
Verma, Gaurav
|
|
|
172 |
C |
p.
|
artikel
|
| 20 |
Inherent safety enhancement by design optimization of a floating absorber for safety at transient (FAST) in an advanced burner reactor
|
Lee, Seongmin
|
|
|
172 |
C |
p.
|
artikel
|
| 21 |
In-situ testing of Czech bentonite for radioactive waste disposal in Mock-up Josef experiment
|
Šťástka, J.
|
|
|
172 |
C |
p.
|
artikel
|
| 22 |
Mitigation of long-term station blackout accident of advanced boiling water reactors
|
Lee, Min
|
|
|
172 |
C |
p.
|
artikel
|
| 23 |
Numerical simulation of jet breakup phenomenon during severe accident of sodium-cooled fast reactor using MPS method
|
Xu, Yihua
|
|
|
172 |
C |
p.
|
artikel
|
| 24 |
Numerical simulation of sodium mist behavior in turbulent Rayleigh-Bénard convection using new developed mist models
|
Ohira, Hiroaki
|
|
|
172 |
C |
p.
|
artikel
|
| 25 |
Numerical study on pressure oscillations amplitude distribution induced by water flow into pipe filled with steam
|
Quddus, Abdul
|
|
|
172 |
C |
p.
|
artikel
|
| 26 |
On integrating Monte Carlo calculations in and around near-critical configurations – I. Methodology
|
Brovchenko, M.
|
|
|
172 |
C |
p.
|
artikel
|
| 27 |
Optimal design of separation cascades using the whale optimization algorithm
|
Dadashzadeh, S.
|
|
|
172 |
C |
p.
|
artikel
|
| 28 |
Particulate Fuel Modeling of MC2-3 using Iterative Local Spatial Self-shielding Method
|
Park, H.
|
|
|
172 |
C |
p.
|
artikel
|
| 29 |
Reactor physics study of square and hexagonal lattice cell using MANTRA ( M ethod of Ch A racteristics based N eutron TRAnsport Code) coupled with resonance treated multi energy group cross section library
|
Mazumdar, Tanay
|
|
|
172 |
C |
p.
|
artikel
|
| 30 |
REGAL International Program: Analysis of experimental data for depletion code validation
|
Eysermans, J.
|
|
|
172 |
C |
p.
|
artikel
|
| 31 |
Research on proportional method for experimental facility of lead-based fast reactor with natural circulation
|
Zhao, Pengcheng
|
|
|
172 |
C |
p.
|
artikel
|
| 32 |
Research on the energy characteristics of reactor coolant pump under flow coastdown transient
|
Daoxing, Ye
|
|
|
172 |
C |
p.
|
artikel
|
| 33 |
Statistical characterization of liquid film fluctuations during gas-liquid two-phase counter-current flow in a 1/30 scaled-down test facility of a pressurized water reactor (PWR) hot leg
|
Astyanto, Achilleus Hermawan
|
|
|
172 |
C |
p.
|
artikel
|
| 34 |
Virtual analog of uranium-water subcritical assembly
|
Kiryukhin, P.K.
|
|
|
172 |
C |
p.
|
artikel
|
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