| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A CFD study on radionuclides diffusion and dose assessment in Daya Bay nuclear power plant
|
He, Sihong
|
|
|
173 |
C |
p.
|
artikel
|
| 2 |
A new numerical method for complex two-phase discharge force based on ARSAC program
|
Wu, Dan
|
|
|
173 |
C |
p.
|
artikel
|
| 3 |
A numerical study on multi-nozzle spray cooling of downward-facing heater surface
|
Fang, Di
|
|
|
173 |
C |
p.
|
artikel
|
| 4 |
Application of artificial neural network for assembly homogenized equivalence parameter generation
|
Dzianisau, Siarhei
|
|
|
173 |
C |
p.
|
artikel
|
| 5 |
A reliability-based multidisciplinary design parallel optimization method based on double-layer approximation model for nuclear fuel assembly bottom nozzle
|
Wan, Changfu
|
|
|
173 |
C |
p.
|
artikel
|
| 6 |
A tree-based automated machine learning approach of the obstructed view factor of thermal radiation in nuclear pebble beds
|
Wu, Hao
|
|
|
173 |
C |
p.
|
artikel
|
| 7 |
CorTAF-LBE: A full scale subchannel-level thermal-hydraulic characteristics analysis code for LBR core based on OpenFOAM
|
Liu, Kai
|
|
|
173 |
C |
p.
|
artikel
|
| 8 |
Coupling between LOTUS and CTF with DYN3D within a multiscale and multiphysics software development
|
Davies, Sebastian
|
|
|
173 |
C |
p.
|
artikel
|
| 9 |
Design and optimization of three segmented thermoelectric generator for nuclear reactor application
|
Tang, Simiao
|
|
|
173 |
C |
p.
|
artikel
|
| 10 |
Design and simulation of neutron radiography system for an aqueous homogeneous solution reactor
|
Jandaghian, B.
|
|
|
173 |
C |
p.
|
artikel
|
| 11 |
Design considerations and Monte Carlo criticality analysis of spiral plate heat exchangers for Molten Salt Reactors
|
Brady, Christopher
|
|
|
173 |
C |
p.
|
artikel
|
| 12 |
Development and verification of the transient fission matrix combination method for the efficient neutron kinetic simulations
|
Li, Yuehang
|
|
|
173 |
C |
p.
|
artikel
|
| 13 |
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor
|
Singh, Sudhansu Sekhar
|
|
|
173 |
C |
p.
|
artikel
|
| 14 |
Development of modular dynamic code for steam power conversion system in sodium-cooled fast reactor
|
Liu, Shuo
|
|
|
173 |
C |
p.
|
artikel
|
| 15 |
Editorial Board
|
|
|
|
173 |
C |
p.
|
artikel
|
| 16 |
Effect of temperature sampling methods on sphere packed tube heat transfer coefficient determination
|
Yang, Miao
|
|
|
173 |
C |
p.
|
artikel
|
| 17 |
Electrochemical decladding of used nuclear fuel
|
Davis, Brenton
|
|
|
173 |
C |
p.
|
artikel
|
| 18 |
Establishing operator trust in machine learning for enhanced reliability and safety in nuclear Power Plants
|
Najar, Merouane
|
|
|
173 |
C |
p.
|
artikel
|
| 19 |
Experimental study and theoretical development of liquid entrainment in T-junction with double inlets and single inlet of gas phase
|
Shi, Yanggen
|
|
|
173 |
C |
p.
|
artikel
|
| 20 |
Experimental study of two-phase parameters of subcooled boiling flow in a single-side heated rectangular channel
|
Wan, Lingfeng
|
|
|
173 |
C |
p.
|
artikel
|
| 21 |
Experimental study on flow-induced vibration under laminar flow and turbulent flow transition state in helical coiled tube
|
Wang, Ningyuan
|
|
|
173 |
C |
p.
|
artikel
|
| 22 |
Generalized extreme value analysis of efficient evaluation of extreme values in random media criticality calculations
|
Ueki, Taro
|
|
|
173 |
C |
p.
|
artikel
|
| 23 |
Heterogeneous minor actinide recycling in a boiling water reactor
|
Martinez, Eduardo
|
|
|
173 |
C |
p.
|
artikel
|
| 24 |
High-energy radiation shielding characteristics of SeTeSnZn chalcogenide glasses (STSZ ChGs)
|
Saraswat, Vishnu
|
|
|
173 |
C |
p.
|
artikel
|
| 25 |
Impact of Bi2O3 on the glass system B2O3 -TeO2–MgO–PbO on the purpose of radiation shielding efficacy
|
Thabit, Hammam Abdurabu
|
|
|
173 |
C |
p.
|
artikel
|
| 26 |
Improved CFD simulation of water hammer caused by condensation with an enhanced phase change model
|
Xiong, Feng
|
|
|
173 |
C |
p.
|
artikel
|
| 27 |
Improved prompt and delayed photon heating computational methods for fast reactors
|
Zhang, Teng
|
|
|
173 |
C |
p.
|
artikel
|
| 28 |
IMUPF-BIN: A new autonomous search method for radioactive sources
|
Guo, Yunlei
|
|
|
173 |
C |
p.
|
artikel
|
| 29 |
Investigating the possibility of using a mixture of thorium with different fissile materials as a fuel in TRISO particles for the PBMR-400 reactor
|
Mohamed, Shalash A.
|
|
|
173 |
C |
p.
|
artikel
|
| 30 |
Investigation of cross-wavy primary surface structures for heat exchangers of Brayton cycle system using argon
|
Yuan, Tianxin
|
|
|
173 |
C |
p.
|
artikel
|
| 31 |
Machine learning-enabled weather forecasting for real-time radioactive transport and contamination prediction
|
Ayoub, Ali
|
|
|
173 |
C |
p.
|
artikel
|
| 32 |
METAL: Methodology for liquid metal fast reactor core economic design and fuel loading pattern optimization
|
Al-Dawood, Khaldoon
|
|
|
173 |
C |
p.
|
artikel
|
| 33 |
Monte Carlo iterative k-source method for fixed-source calculations in nearly critical subcritical systems
|
Yamamoto, Toshihiro
|
|
|
173 |
C |
p.
|
artikel
|
| 34 |
Neutronic design analysis of CEA Cadarache URANIE subcritical assembly
|
Harzli, K.
|
|
|
173 |
C |
p.
|
artikel
|
| 35 |
Numerical investigations on steam-air condensation heat transfer enhancement outside helical coiled tube
|
Jing, Ruihan
|
|
|
173 |
C |
p.
|
artikel
|
| 36 |
Numerical simulation of SMILE core bypass narrow-slit flow characteristics under power operation conditions
|
Wang, Xiaotian
|
|
|
173 |
C |
p.
|
artikel
|
| 37 |
Numerical simulation of the thermal-hydraulic characteristics of the liquid metal flow across the single-start helical coiled tube bundles
|
Liu, Limin
|
|
|
173 |
C |
p.
|
artikel
|
| 38 |
On load-following operations of small modular reactors
|
Zhang, Zhibo
|
|
|
173 |
C |
p.
|
artikel
|
| 39 |
Prediction and analysis of decay heat transfer in the core of the pebble bed reactor
|
Zhang, Zuoyi
|
|
|
173 |
C |
p.
|
artikel
|
| 40 |
Pressure fluctuation analysis for identifying the CHF approaching condition during subcooled flow boiling through a mini-channel
|
Aziz, Faraz
|
|
|
173 |
C |
p.
|
artikel
|
| 41 |
Relaxation effects in nuclear fuel coupled calculations using serpent-OpenFOAM codes
|
Korinek, Tomas
|
|
|
173 |
C |
p.
|
artikel
|
| 42 |
RHR water intake pipeline special hydraulic phenomenon test verification
|
Hou, Yandong
|
|
|
173 |
C |
p.
|
artikel
|
| 43 |
SIMMER code two-fluid model well-posedness and stability for simulating liquid metal (lead–lithium eutectic), water vapor, and non-condensable gases multi-component multi-phase flows
|
Saraswat, Satya Prakash
|
|
|
173 |
C |
p.
|
artikel
|
| 44 |
Simulation of natural circulation experiments for heavy liquid metal coolant using HYDRA-IBRAE/LM code
|
Ilyasova, O.H.
|
|
|
173 |
C |
p.
|
artikel
|
| 45 |
Simulation of the gas-lift effect for lead and lead-bismuth coolants in HYDRA-IBRAE/LM thermohydraulic code
|
Grudtsyn, Ya.V.
|
|
|
173 |
C |
p.
|
artikel
|
| 46 |
Simulation study on HPR1000-based suppressive containment system under typical accidents
|
Qi, Xiangjie
|
|
|
173 |
C |
p.
|
artikel
|
| 47 |
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger
|
Wang, Heng
|
|
|
173 |
C |
p.
|
artikel
|
| 48 |
Study of neutronic and creep properties of Kanthal APMT for advanced fuel cladding applications
|
Pradhan, Arnold
|
|
|
173 |
C |
p.
|
artikel
|
| 49 |
The depletion reactivity coefficient of the pebble-bed high temperature gas-cooled reactor based on perturbation theory
|
Sheng, Zhongkai
|
|
|
173 |
C |
p.
|
artikel
|
| 50 |
The development of a high-performance combined fission matrix neutron transport and depletion coupled calculation
|
He, Donghao
|
|
|
173 |
C |
p.
|
artikel
|
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