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                             34 gevonden resultaten
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
                             34 gevonden resultaten
 
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