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                             43 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A 3D particle-based simulation of heat and mass transfer behavior in the EAGLE ID1 in-pile test Zhang, Ting

179 C p.
artikel
2 An analysis of the pressure wave propagation by the sodium-water reaction in the printed circuit steam generator using the SWAAM-II code Kim, Taewoo

179 C p.
artikel
3 An efficient digital twin based on machine learning SVD autoencoder and generalised latent assimilation for nuclear reactor physics Gong, Helin

179 C p.
artikel
4 Application of model-order reduction of non-linear time-dependent neutronics via POD-Galerkin projection and matrix discrete empirical interpolation Elzohery, Rabab

179 C p.
artikel
5 Assessment of reactor flow field prediction based on deep learning and model reduction Yang, Jun

179 C p.
artikel
6 A study of the behavior of the floating absorber for safety at transient (FAST) in an innovative sodium-cooled fast reactor (iSFR) Lee, Seongmin

179 C p.
artikel
7 Bayesian belief network-based human reliability analysis methodology for start-up and shutdown operations in nuclear power plants Jo, Wooseok

179 C p.
artikel
8 Comprehensive stainless steel neutron transport libraries validation Schulc, Martin

179 C p.
artikel
9 Computational method for the added mass of fluid imposed on spent fuel storage racks considering three-dimensional flow Deng, Chao

179 C p.
artikel
10 Data assimilation for the burnup distribution applying the three-dimensional variational and artificial neutral network algorithm Guo, Lin

179 C p.
artikel
11 Development and assessment of prognosis digital twin in a NAMAC system Lin, Linyu

179 C p.
artikel
12 Development and verification of the hexagonal core simulation capability of the NECP-X code Liu, Zhouyu

179 C p.
artikel
13 Editorial Board
179 C p.
artikel
14 Experimental and numerical study on the transient heat transfer process for fluoride salt-to-air cooler Chen, Yu-Shuang

179 C p.
artikel
15 Experimental study of explosion characteristics caused by High-Temperature sodium leakage from a heat pipe into air Liu, Shuai

179 C p.
artikel
16 Experimental study on stepping performance of the control rod hydraulic drive system Qin, Benke

179 C p.
artikel
17 Experimental study on the entrainment of the liquid film in the annular channel of the vortex separator Wang, Lingzi

179 C p.
artikel
18 Feasibility of Low-Enriched Uranium Fueled Nuclear Thermal Propulsion in the Low-Thrust Region Below 16klbf Rawlins, Samantha B.

179 C p.
artikel
19 Heat transfer performance of the solid microencapsulated fuel in light water reactors Deng, Qianliang

179 C p.
artikel
20 Impact of reactor neutron spectrum on measured spectrum averaged cross sections Košťál, Michal

179 C p.
artikel
21 Improved design of LBE cooled solid reactor using 3D neutronics thermal-hydraulics coupling method Yang, Qing

179 C p.
artikel
22 Investigating various factors affecting neutron spectrum in the pressure tube in pressurized heavy water reactor design Kastanya, Doddy

179 C p.
artikel
23 Investigation of single pressure point off-line correction in matrix-solved steam pipe network model for digital twins application Sun, Jilin

179 C p.
artikel
24 Investigations of hydrogen hazard mitigation by deliberate ignition in small modular reactor during severe accident using GASFLOW-MPI Wang, Fangnian

179 C p.
artikel
25 Microstructure and mechanical properties of the solidified melt obtained by the in-pile test Mukhamedov, N.Ye.

179 C p.
artikel
26 Neutronic analysis on TRU multi-recycling in PWR-based SMR core loaded with MOX (U-TRU) and FCM (TRU) fueled assemblies Hwang, Dae Hee

179 C p.
artikel
27 Nonlinear state equation and adaptive symplectic algorithm for the control rod drop Zhao, Ke

179 C p.
artikel
28 Numerical simulation of Delayed-SPND response current in NECP-Bamboo Shao, Ruizhi

179 C p.
artikel
29 Online beam orbit correction of MEBT in CiADS based on multi-agent reinforcement learning algorithm Yang, Xuhui

179 C p.
artikel
30 Pin power reconstruction for hexagonal geometry in nodal neutronics program Ants Valtavirta, Ville

179 C p.
artikel
31 Preliminary conceptual design of a moderated micro nuclear reactor core cooled by heat pipe Chai, Xiang

179 C p.
artikel
32 Research on decay heat removal effectiveness in pool-type fast reactor CEFR based on system code SAC-DRACS coupled with CFD software Guo, Jinsong

179 C p.
artikel
33 Research on deterioration evolution trend of primary loop piping in nuclear power plant based on fusion health index Qian, Hong

179 C p.
artikel
34 Retraction notice to “Core design and analysis of a lead-bismuth cooled small modular reactor” [Ann. Nucl. Energy 133 (2019) 511–518/6850] Wang, Chenglong

179 C p.
artikel
35 Study on static characteristics of array electrode capacitance control rod position measurement sensor Li, Yanlin

179 C p.
artikel
36 The feasibility study of the Sub-criticalization of the Holos small modular reactor driven by an electron accelerator Mahdi Firoozabadi, Mohammad

179 C p.
artikel
37 Theory and application of the functional expansion fission matrix He, Donghao

179 C p.
artikel
38 The reconstruction of 3D radiation field based on sparse measurement data Xie, Xingwen

179 C p.
artikel
39 Thermal hydraulic modeling of solid-fueled nuclear thermal propulsion reactors part II: Full-core coupled neutronic and thermal hydraulic analysis Krecicki, M.

179 C p.
artikel
40 Thermo-hydrodynamics of multiple drops impinging simultaneously on the grooved tubular surface and smooth cylindrical surface with different wettabilities Xiao, Lan

179 C p.
artikel
41 The stability criterion based on the spurious pressure oscillation analysis of MPS method Cai, Qinghang

179 C p.
artikel
42 The study on the partition method of two-phase wall drag in the one-dimensional two-fluid model Shen, Mengsi

179 C p.
artikel
43 Treating model inadequacy in fuel performance model calibration by parameter uncertainty inflation Robertson, Gustav

179 C p.
artikel
                             43 gevonden resultaten
 
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