| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comparison study on mechanical models for TRISO fuel particle in HTGR
|
Li, Jian
|
|
|
161 |
C |
p.
|
artikel
|
| 2 |
A linear source scheme for the 2D/1D transport method in SHARK
|
Zhao, Chen
|
|
|
161 |
C |
p.
|
artikel
|
| 3 |
An efficient hybrid multi-level CMFD in space and energy for accelerating the high-fidelity neutron transport calculation
|
Hao, Chen
|
|
|
161 |
C |
p.
|
artikel
|
| 4 |
An enhanced adaptation method for core monitoring systems
|
Dall’Osso, Aldo
|
|
|
161 |
C |
p.
|
artikel
|
| 5 |
A new methodology to speed-up fuel lattice design optimization using decision trees and new objective functions
|
Ortiz-Servin, Juan José
|
|
|
161 |
C |
p.
|
artikel
|
| 6 |
A novel multi-objective shielding optimization method: DNN-PCA-NSGA-Ⅱ
|
Song, Yingming
|
|
|
161 |
C |
p.
|
artikel
|
| 7 |
Bayesian inference of multi-group nuclear data by Monte Carlo sampling method
|
Wu, Qu
|
|
|
161 |
C |
p.
|
artikel
|
| 8 |
Bi2O3 doped B2O3-ZnO glass powder for immobilization of radioactive iodine waste at low temperature
|
Yan, Meng
|
|
|
161 |
C |
p.
|
artikel
|
| 9 |
Contemplation of relative hydraulic conductivity for compacted bentonite in a high-level radioactive waste repository
|
Yoon, Seok
|
|
|
161 |
C |
p.
|
artikel
|
| 10 |
Continuous online monitoring in pressurized water reactors during flexible operation using PLSR-based technique – Case study: Load following test
|
Elsamahy, Mohamed
|
|
|
161 |
C |
p.
|
artikel
|
| 11 |
Design of an experimental test loop for fast spectrum test conditions
|
LaBrier, Daniel
|
|
|
161 |
C |
p.
|
artikel
|
| 12 |
Development and application of Monte Carlo and COMSOL coupling code for neutronics/thermohydraulics coupled analysis
|
Weng, Minghui
|
|
|
161 |
C |
p.
|
artikel
|
| 13 |
Development of IVR-ERVC evaluation method and its application to the SMART
|
Park, Rae-Joon
|
|
|
161 |
C |
p.
|
artikel
|
| 14 |
Editorial Board
|
|
|
|
161 |
C |
p.
|
artikel
|
| 15 |
Effective medium temperature for calculating the Doppler broadening function using Kaniadakis distribution
|
Silva, Marcelo V. da
|
|
|
161 |
C |
p.
|
artikel
|
| 16 |
Effects of a change in the design of cooling water injection on risk reduction in a beam tube rupture
|
Lee, Yoon-Hwan
|
|
|
161 |
C |
p.
|
artikel
|
| 17 |
Fine Mesh Finite Difference acceleration method based on the Generalized Equivalence Theory for the 2-D MOC transport calculation
|
Zhu, Kaijie
|
|
|
161 |
C |
p.
|
artikel
|
| 18 |
Flow-induced vibration of tube bundles considering the effect of periodic fluid force in a rotated triangular tube array
|
Lai, Jiang
|
|
|
161 |
C |
p.
|
artikel
|
| 19 |
Improvement in the accuracy of SPACE prediction for the unblocked FLECHT SEASET reflood tests by data assimilation
|
Tiep, Nguyen Huu
|
|
|
161 |
C |
p.
|
artikel
|
| 20 |
Investigation of water injection on molten Zirconium-Stainless steel pool in IVR strategy
|
Li, Zongyang
|
|
|
161 |
C |
p.
|
artikel
|
| 21 |
Large-break LOCA analysis of CSR1000
|
Gaojian, Dang
|
|
|
161 |
C |
p.
|
artikel
|
| 22 |
LES and URANS study on turbulent flow through 3 × 3 rod bundle with spacer grid and mixing vanes using spectral element method
|
Ju, Haoran
|
|
|
161 |
C |
p.
|
artikel
|
| 23 |
Machine learning application to single channel design of molten salt reactor
|
Turkmen, Mehmet
|
|
|
161 |
C |
p.
|
artikel
|
| 24 |
Melt infiltration through porous debris at temperatures above Solidification: Validation of analytical model
|
Mohsen Hoseyni, Seyed
|
|
|
161 |
C |
p.
|
artikel
|
| 25 |
Monte-Carlo based investigation of individual dosimetry in deep geological repository for high-level nuclear waste with consideration of realistic body postures
|
Pang, Bo
|
|
|
161 |
C |
p.
|
artikel
|
| 26 |
Monte Carlo neutronics benchmarks on nuclear fuel depletion: A review
|
Martinson, Sean P.
|
|
|
161 |
C |
p.
|
artikel
|
| 27 |
Neutronic experiment and analyses of a hybrid tritium breeding blanket mockup for CFETR
|
Ma, Jimin
|
|
|
161 |
C |
p.
|
artikel
|
| 28 |
Neutron thermalization in nuclear graphite: A modern story of a classic moderator
|
Al-Qasir, Iyad I.
|
|
|
161 |
C |
p.
|
artikel
|
| 29 |
Numerical investigation for the heat transfer mechanisms between subchannels of bar rod bundles cooled by liquid sodium
|
Wang, X.A.
|
|
|
161 |
C |
p.
|
artikel
|
| 30 |
Numerical investigation on thermohydraulic performance of high temperature hydrogen in twisted rod channels
|
Fang, Yuliang
|
|
|
161 |
C |
p.
|
artikel
|
| 31 |
On the importance of target accuracy assessments and data assimilation for the co-development of nuclear data and fast reactors: MYRRHA and ESFR
|
Romojaro, P.
|
|
|
161 |
C |
p.
|
artikel
|
| 32 |
On the use of criticality and depletion benchmarks for verification of nuclear data
|
Fiorito, L.
|
|
|
161 |
C |
p.
|
artikel
|
| 33 |
Predicting and optimizing the thermal-hydraulic, natural circulation, and neutronics parameters in the NuScale nuclear reactor using nanofluid as a coolant via machine learning methods through GA, PSO and HPSOGA algorithms
|
Rahnama, Z.
|
|
|
161 |
C |
p.
|
artikel
|
| 34 |
Preliminary development and validation of ACENA code for heavy liquid metal-gas two phase flow simulation
|
Chen, Yutong
|
|
|
161 |
C |
p.
|
artikel
|
| 35 |
Pressurizer water level control with estimation of primary circuit coolant mass in nuclear power plants via robust observer based dynamic sliding mode control
|
Mostafavi, S.M.
|
|
|
161 |
C |
p.
|
artikel
|
| 36 |
Reactivity determination in a subcritical reactor: Computational, analytical and experimental methods
|
Malkawi, Salaheddin
|
|
|
161 |
C |
p.
|
artikel
|
| 37 |
Recent progresses on thermal–hydraulics evaluations of accident tolerant fuel cladding materials
|
He, Mingfu
|
|
|
161 |
C |
p.
|
artikel
|
| 38 |
Research on eccentricity performance of winding wire capacitance rod position measurement sensor
|
Li, Yanlin
|
|
|
161 |
C |
p.
|
artikel
|
| 39 |
Research on power flattening method and neutron characteristic analysis of a megawatt-class space gas-cooled fast reactor
|
He, Yuhao
|
|
|
161 |
C |
p.
|
artikel
|
| 40 |
Sensitivity analysis of in-pile critical heat flux experiments in TREAT for characterization of RIA power-transient effects
|
Seo, Seok Bin
|
|
|
161 |
C |
p.
|
artikel
|
| 41 |
Theoretical study on the Passively Decay Heat Removal System and the primary loop flow rate of NuScale SMR
|
Fakhrarei, A.
|
|
|
161 |
C |
p.
|
artikel
|
| 42 |
Thermal scattering law data generation for hydrogen bound in zirconium hydride based on the phonon density of states from first-principles calculations
|
Zu, Tiejun
|
|
|
161 |
C |
p.
|
artikel
|
| 43 |
The scaling technology in nuclear reactor thermal hydraulic
|
Wang, L.S.
|
|
|
161 |
C |
p.
|
artikel
|
| 44 |
The utilization of ThO2 fuel discharged from an ADS in the Multi-Application Small Light Water Reactor (MASLWR)
|
Ali, A.M.M.
|
|
|
161 |
C |
p.
|
artikel
|
| 45 |
Uncertainty comparison between ENDF/B-VIII.0 and ENDF/B-VII.1 for fast reactor BN-600 using high-precision sampling method
|
Ma, Xubo
|
|
|
161 |
C |
p.
|
artikel
|
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