nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A model fine-tuning approach for robust anomaly detection and isolation in multi-sensor system of nuclear power plants
|
Yi, Shuang |
|
|
205 |
C |
p. |
artikel |
2 |
An assessment of UO2 and ATF concept fuel performance modeling demands against current experimental capabilities under LOCA conditions
|
Probert, Allison |
|
|
205 |
C |
p. |
artikel |
3 |
A numerical method for two-dimensional transient nonlinear convection-diffusion equations
|
Meng, Xiangyuan |
|
|
205 |
C |
p. |
artikel |
4 |
A once-through artificial neural network approach for used nuclear fuel inverse depletion analysis: A comparative study
|
Khuwaileh, Bassam A. |
|
|
205 |
C |
p. |
artikel |
5 |
Application of machine learning methods for spent fuel characterization based on gamma spectrometry measurements
|
Kirchknopf, Péter |
|
|
205 |
C |
p. |
artikel |
6 |
Application of reinforcement learning to deduce nuclear power plant severe accident scenario
|
Song, Seok Ho |
|
|
205 |
C |
p. |
artikel |
7 |
A review of natural circulation flow in integral effect test facilities
|
Kim, Yeon-Sik |
|
|
205 |
C |
p. |
artikel |
8 |
A study on the influence of closure model and numerical technology on the stability of two-fluid model
|
Zhang, Hao |
|
|
205 |
C |
p. |
artikel |
9 |
Capability for processing photonuclear data in nuclear data processing code NECP-Atlas
|
Wu, Hongchun |
|
|
205 |
C |
p. |
artikel |
10 |
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)
|
Jang, Kyung Bae |
|
|
205 |
C |
p. |
artikel |
11 |
Corrigendum to “Comparison of MSLB transient results using the 3D coupled code TRACEv5p05/PARCS and the system thermal hydraulic code RELAP5” [Ann. Nucl. Energy 203 (2024) 110518]
|
Stefanova, Antoaneta |
|
|
205 |
C |
p. |
artikel |
12 |
Corrigendum to “REGAL International Program: Analysis of experimental data for depletion code validation” [Ann. Nucl. Energy 172 (2022) 109057]
|
Eysermans, J. |
|
|
205 |
C |
p. |
artikel |
13 |
Decay heat removal in sodium cooled fast Reactors-An overview
|
Vaidyanathan, G. |
|
|
205 |
C |
p. |
artikel |
14 |
Editorial Board
|
|
|
|
205 |
C |
p. |
artikel |
15 |
Effect of ZrO2 on physical and radiation shielding properties of tellurium −lead- calcium −borate (TPCB)glass system
|
El-Khayatt, Ahmed M. |
|
|
205 |
C |
p. |
artikel |
16 |
Generation of high-resolution thermal scattering laws for solid moderators using fast Fourier transforms
|
Wormald, J.L. |
|
|
205 |
C |
p. |
artikel |
17 |
Impact of radioactive emissions from the Laguna Verde nuclear power plant using CALPUFF
|
Hernández-Garces, Anel |
|
|
205 |
C |
p. |
artikel |
18 |
Investigation of the Cd-Ratio difference method to measure the cross section of 186W(n,γ)187W at the Jordan Research and Training reactor
|
Al-Khasawneh, Kafa |
|
|
205 |
C |
p. |
artikel |
19 |
Multi-objective reinforcement learning-based approach for pressurized water reactor optimization
|
Seurin, Paul |
|
|
205 |
C |
p. |
artikel |
20 |
Neutronic assessment and optimization of ACP-100 reactor core models to achieve unit multiplication and radial power peaking factor
|
Ishraq, Md. Abidur Rahman |
|
|
205 |
C |
p. |
artikel |
21 |
Numerical analysis and structural optimization of a DLC coated capacitance wire-mesh sensor for measuring liquid metal-gas two-phase distribution
|
Bao, Ruiqi |
|
|
205 |
C |
p. |
artikel |
22 |
Numerical simulation on particle sedimentation in water-filled pool using CFD-DEM method
|
Na, Hanbee |
|
|
205 |
C |
p. |
artikel |
23 |
Numerical study of the effect of helical fuel rod geometry on single-phase flow and heat transfer characteristics
|
Fu, Junsen |
|
|
205 |
C |
p. |
artikel |
24 |
Optimization of pressure tube-type measuring instrument for floating nuclear power plant
|
Li, Dongyang |
|
|
205 |
C |
p. |
artikel |
25 |
PLEIADES: A numerical framework dedicated to the multiphysics and multiscale nuclear fuel behavior simulation
|
Bernaud, Stéphane |
|
|
205 |
C |
p. |
artikel |
26 |
Quantifying uncertainty induced by scattering angle distribution using maximum entropy method
|
Maruyama, Shuhei |
|
|
205 |
C |
p. |
artikel |
27 |
Radiation survey for Taiwan research reactor vessel
|
Huang, Jhih-Jhong |
|
|
205 |
C |
p. |
artikel |
28 |
Research on fault diagnosis and fault location of nuclear power plant equipment
|
Huang, Xue-ying |
|
|
205 |
C |
p. |
artikel |
29 |
Research on fine modeling of dispersion fuel plate based on lattice method
|
Chen, Yuqing |
|
|
205 |
C |
p. |
artikel |
30 |
Research on pin-by-pin calculation method of rectangular mesh based on quasi-diffusion theory
|
Zhuang, Kun |
|
|
205 |
C |
p. |
artikel |
31 |
Revisited analysis of the PUIREX 2008 decay heat experiment in the Phénix Sodium Fast Reactor
|
da Cunha, Dorian |
|
|
205 |
C |
p. |
artikel |
32 |
Simulation and experimental verification for Rh-SPND burnup effect
|
Wu, Tingyu |
|
|
205 |
C |
p. |
artikel |
33 |
The flow field and convective heat transfer in the unit structure of heat exchangers by using acoustic waves
|
Ou, Yun |
|
|
205 |
C |
p. |
artikel |
34 |
Use of rational approximations for phonon density of states in evaluation of neutron thermal scattering law
|
Keshavamurthy, R.S. |
|
|
205 |
C |
p. |
artikel |