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                             51 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Al–B4C-(Gd, Gd2O3) composite materials: Synthesis and characterization for neutron shielding applications Gaylan, Yasin

56 12 p. 5201-5211
artikel
2 Analysis of double-ended guillotine break accident of surge line in ACP100 based on coupling method: Development and validation of the coupling method Miao, Fan

56 12 p. 5377-5385
artikel
3 Analysis of radiation conditions in the CFETR ion cyclotron resonance heating antenna Wang, Gaoxiang

56 12 p. 5037-5042
artikel
4 Analysis of the atomic ratio of H and Zr effect on the neutronics parameters of ZrH moderated space nuclear reactor Zou, Xiaoliang

56 12 p. 5014-5021
artikel
5 A novel irradiation module for ANICCA fuel cycle code based on multi-task learning Casas-Molina, Victor J.

56 12 p. 5175-5181
artikel
6 A PHITS based-computational model of a TRIGA-fueled subcritical reactor for gamma dose mapping Cruz, Jowi Rapha P.

56 12 p. 5339-5345
artikel
7 Applicability analysis of induction bending process to P91 piping of PGSFR by high-temperature fatigue test Na, Tae-Won

56 12 p. 5190-5200
artikel
8 A review of COHRISK: Multihazard risk quantification software for nuclear power plants Choi, Eujeong

56 12 p. 5281-5290
artikel
9 A simplified SP3 NEM solver within a unified formulation for pin-by-pin core multi-group calculations Wang, Sicheng

56 12 p. 5078-5095
artikel
10 Assessing the Phebus FPT-1 experiment: Insights from MELCOR 2.2 and ASYST codes Mician, Peter

56 12 p. 5136-5144
artikel
11 Assessment of environmental hazard impacts in building materials (Marble), Gabal El-Galala El-Bahariya, Northeastern Desert, Egypt Hanfi, M.Y.

56 12 p. 4966-4974
artikel
12 Assessment of Look-up tables for the prediction of heat transfer coefficient distribution in rod bundles cooled by supercritical water Sardar, Rashed MD.

56 12 p. 5346-5356
artikel
13 A three-dimensional CFD simulation of corium jet breakup in intensive vapor generation condition Eom, Jeong-Hyun

56 12 p. 5269-5280
artikel
14 CFD simulation of thermal stratification and mixing in a Nordic BWR pressure suppression pool Wang, Xicheng

56 12 p. 5357-5376
artikel
15 Comparative analysis of machine learning-based dose assessment algorithms for TL dosimetry Lee, Soohyeok

56 12 p. 5414-5421
artikel
16 Confirmation bias, information selection, and belief reinforcement about the safety/risk of nuclear spent fuel storage facilities Lee, Daeyoun

56 12 p. 4975-4982
artikel
17 Continuous mapping of nuclear reactor core power using artificial neural network even in the presence of inactive detectors Talon, João D.

56 12 p. 4983-4996
artikel
18 Defect monitoring system of the internal structures of a sodium fast reactor using an artificial intelligence model Byun, Hyungi

56 12 p. 5405-5413
artikel
19 Design of the 500 MHz 2-cell superconducting cavity for the SILF Sun, Yanbing

56 12 p. 5068-5077
artikel
20 Effect of thermal neutron flux on borate and silicate glasses: Experimental and theoretical investigation for distribution, decay period, and absorbed dose rate of produced isotopes Tashlykov, O.L.

56 12 p. 5222-5230
artikel
21 Effects of electrode configuration on the current density distribution of the electrolytic reducer Hur, Jin-Mok

56 12 p. 4951-4958
artikel
22 Evaluation of particle-capturing ability of a hydrogel-based surface decontamination agent using simulated nuclear fallout particles Kim, Sung-Wook

56 12 p. 5386-5395
artikel
23 Experimental study on practical application of optical fiber sensor (OFS) for high-temperature system Kim, Byeongyeon

56 12 p. 5182-5189
artikel
24 Feasibility of a position-sensitive Cherenkov radiation detector using a reflector-coated liquid light guide Lee, Sangjun

56 12 p. 5231-5238
artikel
25 Heavy metal loading effects on special nuclear material and waste of an uprated Indonesian Reaktor Daya Eksperimental Mulyana, Dany

56 12 p. 5239-5247
artikel
26 Hydrodynamics coupled circulating-fuel reactor equations in comoving frame and their analytical solutions for molten salt reactors Yılmazer, Ayhan

56 12 p. 4997-5013
artikel
27 Imbalanced data fault diagnosis method for nuclear power plants based on convolutional variational autoencoding Wasserstein generative adversarial network and random forest Guo, Jun

56 12 p. 5055-5067
artikel
28 Impact of choice of fragility approaches on seismic risk quantification of nuclear power plants Kasapoglu, Baris

56 12 p. 5154-5174
artikel
29 Improvement of macroscopic turbulence model for subchannel analysis in the rod bundle array Kim, Seok

56 12 p. 5118-5135
artikel
30 Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX Wu, Hongchun

56 12 p. 5305-5312
artikel
31 Leveraging physics-informed neural computing for transport simulations of nuclear fusion plasmas Seo, J.

56 12 p. 5396-5404
artikel
32 Lifetime thermal analysis of the CANDU spent fuel storage canister at the Wolsung site Lee, Tae Gang

56 12 p. 5320-5329
artikel
33 Loss of power accident analysis for the HCCR blanket Jin, Hyung Gon

56 12 p. 4947-4950
artikel
34 Measurement of production cross-sections of natTi(p,x)43K,43,44m,44g,46g,47,48Sc,48V reactions up to 50 MeV Moon, Dal-Ho

56 12 p. 5022-5027
artikel
35 Mesh morphing-based pre-processing and numerical simulation of blockage accident in lead–bismuth fast reactor fuel assembly Sun, Hao

56 12 p. 5248-5256
artikel
36 Methodology for estimating the contribution of forest fires in loss of offsite power events Lim, Joonseok

56 12 p. 5096-5105
artikel
37 Microstructure response and sodium corrosion behavior of ferritic-martensitic steel after proton irradiation Lee, Jeonghyeon

56 12 p. 5028-5036
artikel
38 Neutron balance approach for inline critical rod position search calculation in Monte Carlo reactor analysis Jo, YuGwon

56 12 p. 5297-5304
artikel
39 Numerical study on the size effect on the mixing in 2×1, 3×3 and 5×5 rod bundle subchannels Han, Bin

56 12 p. 5106-5117
artikel
40 Optimizing spent nuclear fuel cask loading for VVER-440 fuel Lovecký, M.

56 12 p. 5048-5054
artikel
41 Preliminary neutronics design and analysis of lithium heat pipe cooled space reactor with low-enriched uranium Zou, Xiaoliang

56 12 p. 5330-5338
artikel
42 Preparation and radiation shielding features of high density, transparent borosilicate glasses with different Bi2O3 contents Sayyed, M.I.

56 12 p. 5043-5047
artikel
43 Research on magnetostrictive liquid level gauge for water level measurement of steam generator Duan, Shuiqiang

56 12 p. 5422-5427
artikel
44 Study of circulating liquid fuel in a 1D critical system with thermal feedback Caprais, Mathis

56 12 p. 5212-5221
artikel
45 Study on quantitative interpretation of uranium spectral gamma-ray logging based on machine learning algorithm Zhang, Yan

56 12 p. 4959-4965
artikel
46 Study on the effect of geometry and material property on collapse pressure of a helical steam generator tube under external pressure Youn, Gyo-Geun

56 12 p. 5257-5268
artikel
47 Technical reviewers for Nuclear Engineering and Technology, 2024
56 12 p. 5437-5451
artikel
48 Thermal dynamics aspect identification of loop heat pipe with capillary tube wick using nonlinear autoregressive exogenous neural network Setyo Pambudi, Yoyok Dwi

56 12 p. 5145-5153
artikel
49 Towards accurate dose assessment for emergency industrial radiography source retrieval operations: A preliminary study of 4D Monte Carlo dose calculations Moon, Sungho

56 12 p. 5428-5436
artikel
50 “Two-dimensional distribution reconstruction and emittance diagnostics of proton beam phase space using tomography” Dang, Jeong-Jeung

56 12 p. 5291-5296
artikel
51 Uranium quantification in radioactive waste drums using In-Situ Object Counting System (ISOCS) for safeguards purposes Ahn, Jihyun

56 12 p. 5313-5319
artikel
                             51 gevonden resultaten
 
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