| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Aerosol pool scrubbing phenomena during the containment depressurization venting. Part I: Scaling analysis
|
Gao, Z.C.
|
|
|
165 |
C |
p.
|
artikel
|
| 2 |
A fuzzy fault accommodation method for nuclear power plants under actuator stuck faults
|
Wang, Pengfei
|
|
|
165 |
C |
p.
|
artikel
|
| 3 |
Analysis of double-layered buffer in high-level waste repository
|
Tan, Yunzhi
|
|
|
165 |
C |
p.
|
artikel
|
| 4 |
Analytical assessment of VVER-1000 fuel assembly deformation in loss of coolant accident
|
Taheranpour, N.
|
|
|
165 |
C |
p.
|
artikel
|
| 5 |
Analytical nodal method for solution of neutron diffusion equation in polar coordinates
|
Raj, Manish
|
|
|
165 |
C |
p.
|
artikel
|
| 6 |
A new method to solve the neutron transport problem of spherical structure
|
Liu, Yang
|
|
|
165 |
C |
p.
|
artikel
|
| 7 |
An insight into the flow field characteristics of the high temperature liquid Sodium (Na) with cavitation effects in the 600 MW fast reactor system
|
Xie, Zhongliang
|
|
|
165 |
C |
p.
|
artikel
|
| 8 |
An uncertainty quantification method relevant to material test reactors
|
Patel, Vishal
|
|
|
165 |
C |
p.
|
artikel
|
| 9 |
A pure dynamic Monte Carlo code for the neutronic analysis of nuclear reactors
|
Ajami, Mona
|
|
|
165 |
C |
p.
|
artikel
|
| 10 |
A semi-empirical model of radiolytic gas bubble formation and evolution during criticality excursions in uranyl nitrate solutions for nuclear criticality safety assessment
|
Winter, George E.
|
|
|
165 |
C |
p.
|
artikel
|
| 11 |
A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP
|
Jyotish, Nand Kumar
|
|
|
165 |
C |
p.
|
artikel
|
| 12 |
A two-phase three-field modeling framework for heat pipe application in nuclear reactors
|
Shi, Shanbin
|
|
|
165 |
C |
p.
|
artikel
|
| 13 |
Bayesian inverse uncertainty quantification of a MOOSE-based melt pool model for additive manufacturing using experimental data
|
Xie, Ziyu
|
|
|
165 |
C |
p.
|
artikel
|
| 14 |
Calculation of delayed neutron precursors’ transit time in the external loop during a flow velocity transient in a Molten Salt Reactors
|
Diniz, Rodrigo Costa
|
|
|
165 |
C |
p.
|
artikel
|
| 15 |
Chemical spectral shift control method for VVER-1000 LEU fuel assembly benchmark
|
Elzayat, T.
|
|
|
165 |
C |
p.
|
artikel
|
| 16 |
Comparative study of meta-heuristic algorithms for reactor fuel reloading optimization based on the developed BP-ANN calculation method
|
Li, Zhan
|
|
|
165 |
C |
p.
|
artikel
|
| 17 |
Comparison between APOLLO2 and MCNP6 on depletion calculations for an Er-SHB PWR fuel assembly
|
Pergreffi, Roberto
|
|
|
165 |
C |
p.
|
artikel
|
| 18 |
Comparison of probabilistic and deterministic methods for calculation of kinetic parameters of HWZPR
|
Taghizadeh, Leili
|
|
|
165 |
C |
p.
|
artikel
|
| 19 |
Coupled MELCOR/COCOMO analysis on quench of ex-vessel debris beds
|
Chen, Yangli
|
|
|
165 |
C |
p.
|
artikel
|
| 20 |
Cross sections polynomial axial expansion within the APOLLO3® 3D characteristics method
|
Gammicchia, A.
|
|
|
165 |
C |
p.
|
artikel
|
| 21 |
Design and performance analysis of a mobile, land-based micro-reactor
|
Passons, Branden
|
|
|
165 |
C |
p.
|
artikel
|
| 22 |
Design of computerized operator support system for technical specification monitoring
|
Lee, Subong
|
|
|
165 |
C |
p.
|
artikel
|
| 23 |
Development and validation of a time-dependent deterministic model for neutron noise on CROCUS experimental measurements
|
Brighenti, A.
|
|
|
165 |
C |
p.
|
artikel
|
| 24 |
Development of a dynamic event tree (DET) to analyze SBO accident in VVER-1000/V446 nuclear reactor
|
Amirsoltani, M.E.
|
|
|
165 |
C |
p.
|
artikel
|
| 25 |
Development of SARAX code system for full-range spectrum adaptability in advanced reactor analysis
|
Wei, Linfang
|
|
|
165 |
C |
p.
|
artikel
|
| 26 |
Dynamics of a slender structure subjected to annular flow, application to a nuclear reactor core guide tube
|
Ricciardi, Guillaume
|
|
|
165 |
C |
p.
|
artikel
|
| 27 |
Editorial Board
|
|
|
|
165 |
C |
p.
|
artikel
|
| 28 |
Effect of geometry and upstream stagnation thermodynamic parameters on CO2 choked flow through orifices
|
Huang, Jiajian
|
|
|
165 |
C |
p.
|
artikel
|
| 29 |
Effects of additives on the thermal stability of silver tellurite glass system
|
Kang, Hyun Woo
|
|
|
165 |
C |
p.
|
artikel
|
| 30 |
Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysis
|
Alraisi, Ali
|
|
|
165 |
C |
p.
|
artikel
|
| 31 |
Efficient MC–CMFD multiphysics
|
Harper, S.M.
|
|
|
165 |
C |
p.
|
artikel
|
| 32 |
Evaluation of a freeze-tolerant decay heat removal system redundancy for fluoride salt-cooled high-temperature reactors (FHR)
|
Liu, Maolong
|
|
|
165 |
C |
p.
|
artikel
|
| 33 |
Experimental analysis of step reactivity insertion effect on reactor power, fuel temperature and reactor period in BAEC TRIGA research reactor
|
Hossain, Nazmul
|
|
|
165 |
C |
p.
|
artikel
|
| 34 |
Experimental investigation on pressure drop characteristics of two-phase flow in a rod bundle geometry under high pressure conditions
|
Gui, Miao
|
|
|
165 |
C |
p.
|
artikel
|
| 35 |
Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions
|
Sun, Hao
|
|
|
165 |
C |
p.
|
artikel
|
| 36 |
Extension of SCALE/Sampler’s sensitivity analysis
|
Bostelmann, Friederike
|
|
|
165 |
C |
p.
|
artikel
|
| 37 |
Fractional scaling analysis for the thermal hydraulic behavior of pressurizer
|
Wang, C.
|
|
|
165 |
C |
p.
|
artikel
|
| 38 |
From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction
|
Sun, Ruiyu
|
|
|
165 |
C |
p.
|
artikel
|
| 39 |
Gamma dose rates from a spent UO2 fuel Assembly: Calculations vs measurements
|
Pergreffi, Roberto
|
|
|
165 |
C |
p.
|
artikel
|
| 40 |
Implementation of a built-in self-test for nuclear power plant FPGA-based safety-critical control systems
|
Lin, Zequn
|
|
|
165 |
C |
p.
|
artikel
|
| 41 |
Implementation of two-phase gas transport into VERA for molten salt reactor analysis
|
Taylor, Zack
|
|
|
165 |
C |
p.
|
artikel
|
| 42 |
Internal model control based proportional-integral controller with class topper optimization for power control of molten salt breeder reactor core
|
Pradhan, Subrat Kumar
|
|
|
165 |
C |
p.
|
artikel
|
| 43 |
Liquid lead flow-accelerated corrosion testing with the rotating cage set-up: A CFD optimisation
|
Ali, Abdelmagid E.A.
|
|
|
165 |
C |
p.
|
artikel
|
| 44 |
Manufacturing LEU-foil annular target in Brazil
|
Durazzo, Michelangelo
|
|
|
165 |
C |
p.
|
artikel
|
| 45 |
Novel simulation technique of radioactive aerosol substances propagation into the motionless atmosphere suddenly disseminated by wind to surrounding environment
|
Pecha, Petr
|
|
|
165 |
C |
p.
|
artikel
|
| 46 |
On a characteristic method for the S N neutron transport equation
|
Wang, Dean
|
|
|
165 |
C |
p.
|
artikel
|
| 47 |
One dimensional analytical model considering end effects for analysis of electromagnetic pressure characteristics of annular linear induction electromagnetic pump
|
Zhang, Zhenyang
|
|
|
165 |
C |
p.
|
artikel
|
| 48 |
On the stability of algorithms for enforcing xenon equilibrium
|
Cosgrove, P.
|
|
|
165 |
C |
p.
|
artikel
|
| 49 |
On the use of average power in predicting radioisotope productions
|
Kastanya, Doddy
|
|
|
165 |
C |
p.
|
artikel
|
| 50 |
Optical and thermal visualization of quench front on hot wall during reflood
|
Kim, Woo Shik
|
|
|
165 |
C |
p.
|
artikel
|
| 51 |
Optimal study of swordfish fin microchannel heat exchanger for the next generation nuclear power conversion system of lead-based reactor
|
Lu, Yiming
|
|
|
165 |
C |
p.
|
artikel
|
| 52 |
Preliminary assessments of variations in the form-function-based maximum pin power in CANDU analyses
|
Kastanya, Doddy
|
|
|
165 |
C |
p.
|
artikel
|
| 53 |
Pressure drop and flow characteristics in partially blocked wire wrapped rod bundles
|
Bovati, Octavio
|
|
|
165 |
C |
p.
|
artikel
|
| 54 |
Proliferation resistance assessment of a typical pebble bed reactor fuel
|
Mulyana, Dany
|
|
|
165 |
C |
p.
|
artikel
|
| 55 |
Propagation of VHTRC manufacturing uncertainties with RAVEN/PHISICS
|
Rouxelin, Pascal
|
|
|
165 |
C |
p.
|
artikel
|
| 56 |
Quasi-differential neutron induced neutron emissions from 235U, and 239Pu
|
Mohindroo, Kumar S.
|
|
|
165 |
C |
p.
|
artikel
|
| 57 |
Reactivity worth measurement of the lead target on VENUS-II light water reactor and validation of evaluated nuclear data
|
Jiang, Wei
|
|
|
165 |
C |
p.
|
artikel
|
| 58 |
Research on non-uniform control rod system of PWR
|
Liu, Cheng
|
|
|
165 |
C |
p.
|
artikel
|
| 59 |
Research on robustness of five typical data-driven fault diagnosis models for nuclear power plants
|
Li, Jiangkuan
|
|
|
165 |
C |
p.
|
artikel
|
| 60 |
Research on short term prediction method of thermal hydraulic transient operation parameters based on automated deep learning
|
Li, Xiangyu
|
|
|
165 |
C |
p.
|
artikel
|
| 61 |
Research on the influence of chemical reaction model over MCCI heat transfer process
|
Cao, Ying
|
|
|
165 |
C |
p.
|
artikel
|
| 62 |
Risk analysis virtual ENvironment for dynamic event tree-based analyses
|
Alfonsi, Andrea
|
|
|
165 |
C |
p.
|
artikel
|
| 63 |
Robust controller design for small pressurized water reactors using non-smooth optimization
|
Wang, Pengfei
|
|
|
165 |
C |
p.
|
artikel
|
| 64 |
Sensitivity analysis of in-pile CHF experiments in the TREAT facility: Characterization of impacts of fuel system thermal properties
|
Hernandez, Richard
|
|
|
165 |
C |
p.
|
artikel
|
| 65 |
Simulation-based methodology to assess the lattice defects creation as energy storing process
|
Ponciroli, Roberto
|
|
|
165 |
C |
p.
|
artikel
|
| 66 |
Single neutron tracking method for calculating the probability of survival based on the RMC code
|
Jia, Conglong
|
|
|
165 |
C |
p.
|
artikel
|
| 67 |
Site selection for radioactive waste disposal facility by GIS based multi criteria decision making
|
Bilgilioğlu, Süleyman Sefa
|
|
|
165 |
C |
p.
|
artikel
|
| 68 |
Study on the representativeness of airborne effluent sampling in the stack of a high-temperature gas-cooled pebble-bed modular reactor
|
Sun, Qi
|
|
|
165 |
C |
p.
|
artikel
|
| 69 |
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors
|
Loirec, C. Le
|
|
|
165 |
C |
p.
|
artikel
|
| 70 |
The assembly homogeneous few-group constants generation method for PWR based on machine learning
|
Tan, Kai
|
|
|
165 |
C |
p.
|
artikel
|
| 71 |
The cross section measurements of 131X produced in 238U(n,f) reaction induced by 14 MeV neutron
|
Yang, Luocheng
|
|
|
165 |
C |
p.
|
artikel
|
| 72 |
The dynamical system scaling analysis for single-phase integral test facilities
|
Liu, Zihan
|
|
|
165 |
C |
p.
|
artikel
|
| 73 |
The influence of internal flow on the nonlinear dynamics of a flexible tube in tube bundles subjected to two-phase cross-flow
|
Lai, Jiang
|
|
|
165 |
C |
p.
|
artikel
|
| 74 |
The transient performances of AP1000 IVR under the conservative scenario of DVI line break
|
Wang, Meng
|
|
|
165 |
C |
p.
|
artikel
|
| 75 |
Transformation of classical PSA and DSA into the form of conditional event tree: An approach of human action in time dependent core damage risk
|
Najafi, Alireza
|
|
|
165 |
C |
p.
|
artikel
|
| 76 |
Transition to thorium fuel cycle on a heavy water moderated molten salt reactor by using low enrichment uranium
|
Wu, Jianhui
|
|
|
165 |
C |
p.
|
artikel
|
| 77 |
Uncertainty analysis of infinite multiplication factor and nuclide number density based on the UAM-PWR benchmark with respect to cross sections, fission yields and decay half-life
|
Zu, Tiejun
|
|
|
165 |
C |
p.
|
artikel
|
| 78 |
Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5
|
Shama, Ahmed
|
|
|
165 |
C |
p.
|
artikel
|
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