| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accuracy analysis of RANS turbulent models on predicting thermal stratification in the SUPERCAVNA facility
|
Li, Wenbo
|
|
|
197 |
C |
p.
|
artikel
|
| 2 |
A critical heat flux model for IVR-ERVC application based on the experimental observation
|
Gang, Wang
|
|
|
197 |
C |
p.
|
artikel
|
| 3 |
A new strategy for validating transient neutronic solver using the measurement data during the dynamic rod worth measurement process
|
Bai, Jiahe
|
|
|
197 |
C |
p.
|
artikel
|
| 4 |
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel
|
Ryzhkov, Alexander A.
|
|
|
197 |
C |
p.
|
artikel
|
| 5 |
A numerical investigation of subcooled flow boiling heat transfer in twisted elliptical tubes
|
Di, Xichao
|
|
|
197 |
C |
p.
|
artikel
|
| 6 |
A predictor–corrector Monte Carlo method for thermal radiative transfer equations
|
Shi, Yi
|
|
|
197 |
C |
p.
|
artikel
|
| 7 |
A simulation study of tritium distribution in a 10WM(e) thorium-based molten salt reactor
|
Zeng, You-shi
|
|
|
197 |
C |
p.
|
artikel
|
| 8 |
CFD analysis of coolant mixing in VVER-1000/V320 reactor pressure vessel
|
Böttcher, M.
|
|
|
197 |
C |
p.
|
artikel
|
| 9 |
CFD assessment of RANS turbulence modeling for solidification in internal flows against experiments and higher fidelity LBM-LES phase change model
|
Freile, Ramiro
|
|
|
197 |
C |
p.
|
artikel
|
| 10 |
Development of cyber risk analysis framework for core computational system of TRIGA reactor using graded approach
|
Vechgama, Wasin
|
|
|
197 |
C |
p.
|
artikel
|
| 11 |
Editorial Board
|
|
|
|
197 |
C |
p.
|
artikel
|
| 12 |
Estimation of weight window parameters based on recursive Monte Carlo approach for reactor shielding problems
|
Yadav, Pratibha
|
|
|
197 |
C |
p.
|
artikel
|
| 13 |
Experimental investigation of thermal stratification development in boiling water reactor suppression pools during reactor core isolation cooling system operation
|
Keesling, Dallin
|
|
|
197 |
C |
p.
|
artikel
|
| 14 |
Fragility evaluation of nuclear containment structure subjected to earthquake and subsequent internal pressure
|
Jin, Song
|
|
|
197 |
C |
p.
|
artikel
|
| 15 |
Gas phase interactions between tellurium and organic material in severe nuclear accident scenarios
|
Pasi, Anna-Elina
|
|
|
197 |
C |
p.
|
artikel
|
| 16 |
Health state identification of circulating seawater pump-unit in nuclear power plant based on multi-virtual vibration source fusion in the presence of strong data imbalance
|
Liu, Song
|
|
|
197 |
C |
p.
|
artikel
|
| 17 |
Heat transfer in the argon space of pool-type sodium-cooled fast reactor: Numerical simulation and experimental validation
|
Lu, Daogang
|
|
|
197 |
C |
p.
|
artikel
|
| 18 |
Integration of Level 3 probabilistic risk assessment for nuclear power plants with transportation simulation considering earthquake hazards
|
Shimada, Kazumasa
|
|
|
197 |
C |
p.
|
artikel
|
| 19 |
Inverse method study based on Characteristic Statistic Algorithm (CSA) with application in estimating core states parameters
|
Qian, Zhang
|
|
|
197 |
C |
p.
|
artikel
|
| 20 |
Neural-network-based reconstruction of spent-fuel radioactive distribution in nuclear waste cask
|
Liu, Zhihao
|
|
|
197 |
C |
p.
|
artikel
|
| 21 |
Nuclear material accountancy using momentum-informed muon scattering tomography
|
Bae, JungHyun
|
|
|
197 |
C |
p.
|
artikel
|
| 22 |
Numerical analysis of fluid force on orifice structure of valve disc for nuclear globe valve
|
Zhang, Ao
|
|
|
197 |
C |
p.
|
artikel
|
| 23 |
Numerical simulation of tritium extraction from liquid PbLi by gas–liquid contactor
|
Jiang, Kecheng
|
|
|
197 |
C |
p.
|
artikel
|
| 24 |
On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors
|
Habtemariam, Nahom
|
|
|
197 |
C |
p.
|
artikel
|
| 25 |
Prediction of state transitions in 3D core dynamics and xenon transients based on dynamic mode decomposition
|
Li, Wenhuai
|
|
|
197 |
C |
p.
|
artikel
|
| 26 |
Preliminary analysis of maximum hypothetical accident for a solid core space nuclear reactor power system
|
Li, Ge
|
|
|
197 |
C |
p.
|
artikel
|
| 27 |
Preliminary conceptual design with neutronics and thermal-hydraulics assessments of FuSTAR
|
Zhou, Xingguang
|
|
|
197 |
C |
p.
|
artikel
|
| 28 |
State space modelling development of Micro-High-Temperature Gas-Cooled reactor with helium Brayton cycle
|
Qiu, Leilei
|
|
|
197 |
C |
p.
|
artikel
|
| 29 |
Study on reduction of pressure oscillation in low-velocity steam jet condensation
|
Cao, An
|
|
|
197 |
C |
p.
|
artikel
|
| 30 |
The deterministic neutron transport calculation for the HTR-PM by the three-dimensional method of characteristics code ARCHER
|
Zhu, Kaijie
|
|
|
197 |
C |
p.
|
artikel
|
| 31 |
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors. Part 2: Expediting the solution and applications to a nuclear power plant
|
Kristóf Szarvas, Csongor
|
|
|
197 |
C |
p.
|
artikel
|
| 32 |
Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release
|
Giaccardi, L.
|
|
|
197 |
C |
p.
|
artikel
|
Tijdschrift beschrijving