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                             43 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A data mining framework within the Chinese NPPs operating experience feedback system for identifying intrinsic correlations among human factors Zou, Yanhua
2018
116 C p. 163-170
artikel
2 An adaptive time step control scheme for the transient diffusion equation Boffie, J.
2018
116 C p. 280-289
artikel
3 Analysis of VENUS-2 benchmark using Serpent 2 code Ćalić, Dušan
2018
116 C p. 334-346
artikel
4 A neutron-leakage spectrum model for on-the-fly rehomogenization of nodal cross sections Gamarino, Matteo
2018
116 C p. 257-279
artikel
5 A new high-fidelity neutronics code NECP-X Chen, Jun
2018
116 C p. 417-428
artikel
6 An experimental study on the effect of coaxial circular disk obstacle on helium jet distribution inside the unventilated enclosure of AIHMS facility Prabhakar, Aneesh
2018
116 C p. 347-359
artikel
7 A reduced-basis element method for pin-by-pin reactor core calculations in diffusion and SP 3 approximations Cherezov, Alexey
2018
116 C p. 195-209
artikel
8 A turbulent diffusion model of Rayleigh-Taylor mixing Epstein, Michael
2018
116 C p. 290-295
artikel
9 Benchmark exercise TH-27 on natural convection with steam injection and condensation inside the extended THAI facility Freitag, M.
2018
116 C p. 90-104
artikel
10 CESAM – Code for European severe accident management, EURATOM project on ASTEC improvement Nowack, H.
2018
116 C p. 128-136
artikel
11 Comment on the paper: Goudarzi and Talebi, 2018. Heat removal ability for different orientations of single-phase natural circulation loops using the entransy method. Ann. Nucl. Energ. 111, 509–522 Awad, M.M.
2018
116 C p. 448-449
artikel
12 Coupling methods for HTR-PM primary circuit Lu, Jianan
2018
116 C p. 20-30
artikel
13 Crack initiation, arrest and tearing assessments of a RPV subjected to PTS events Chen, Mingya
2018
116 C p. 143-151
artikel
14 Cross section homogenization for transient calculations in a spatially heterogeneous geometry Dugan, K.
2018
116 C p. 439-447
artikel
15 Editorial Board 2018
116 C p. ii
artikel
16 Effect of chemical etching of fuel cladding surface on crud deposition behavior in simulated primary water of PWRs at 328 °C Baek, Seung Heon
2018
116 C p. 69-77
artikel
17 Effect of wall friction model on predicting emergency core coolant behavior in upper downcomer with direct vessel safety injection using MARS-KS Choi, Chi-Jin
2018
116 C p. 395-406
artikel
18 Evaluation of shielding performance for newly developed composite materials Evans, Beren R.
2018
116 C p. 1-9
artikel
19 Experimental study to estimate the surface wear of nuclear graphite in HTR-PM He, Xiujie
2018
116 C p. 296-302
artikel
20 Feasibility of passive autonomous frequency control operation in a Soluble-Boron-Free small PWR Abdelhameed, Ahmed Amin E.
2018
116 C p. 319-333
artikel
21 General nodal expansion method for multi-dimensional neutronics/thermal-hydraulic coupled problems in pebble-bed core systems Zhou, Xiafeng
2018
116 C p. 10-19
artikel
22 Hybrid MPI-communication for the multi-angular S N parallel sweep on 3-D regular grids Xu, Longfei
2018
116 C p. 407-416
artikel
23 Interfacial behavior of the air-water counter-current two-phase flow in a 1/30 scale-down of pressurized water reactor (PWR) hot leg Badarudin, Apip
2018
116 C p. 376-387
artikel
24 Investigation of flow instability using axially decreased power shape in parallel channels with water at supercritical pressure Shitsi, Edward
2018
116 C p. 152-162
artikel
25 Main results of the European PASSAM project on severe accident source term mitigation Albiol, T.
2018
116 C p. 42-56
artikel
26 Major milestones of HTR development in Germany and still open research issues Allelein, H.-J.
2018
116 C p. 114-127
artikel
27 Matrix formulation for the calculation of nuclear reactivity Suescún-Díaz, Daniel
2018
116 C p. 137-142
artikel
28 Modified Fuchs-Nordheim model for use in reactor pulse measurements Holschuh, Thomas V.
2018
116 C p. 314-318
artikel
29 Molecular dynamics simulation on the corrosion characteristics of iron in liquid lead Liu, Jie
2018
116 C p. 31-41
artikel
30 Multi-level coarse mesh finite difference acceleration with local two-node nodal expansion method Hao, Chen
2018
116 C p. 105-113
artikel
31 On the options for incorporating nuclear data uncertainties in criticality safety assessments for LWR fuel Vasiliev, A.
2018
116 C p. 57-68
artikel
32 Optimization of disposal method and scenario to Reduce High Level Waste Volume and Repository Footprint for HTGR Fukaya, Yuji
2018
116 C p. 224-234
artikel
33 Reducing the loss of offsite power contribution in the core damage frequency of a VVER-1000 reactor by extending the house load operation period Mohsendokht, Massoud
2018
116 C p. 303-313
artikel
34 Retraction notice to “A new strategy to select axial power distribution for thermal hydraulic analysis” [Ann. Nucl. Energy 88 (2016) 265–271] Kim, Kyung-O
2018
116 C p. 450
artikel
35 Sensitivity evaluations of design parameters for various thorium based epithermal reactor (TBER) concepts Choi, Hong Yeop
2018
116 C p. 171-176
artikel
36 Simulation and test of Fuel Handling System for Accelerator Driven Subcritical Reactor Zeng, Meihua
2018
116 C p. 388-394
artikel
37 Systematic hydrogen risk analysis of OPR1000 containment before RPV failure under station blackout scenario Kim, Nam Kyung
2018
116 C p. 429-438
artikel
38 The application of nodal method for dynamic analysis of TRIGA Mark II Jamalipour, M.
2018
116 C p. 360-375
artikel
39 The HEXNEM3 nodal flux expansion method for the hexagonal geometry in the code DYN3D Bilodid, Yuri
2018
116 C p. 187-194
artikel
40 The research on the characteristics of target and core in a gas-cooled ADS with passive safety Wang, Litao
2018
116 C p. 78-89
artikel
41 Thorium-based molten salt SMR as the nuclear technology pathway from a market-oriented perspective Zheng, Gangyang
2018
116 C p. 177-186
artikel
42 Tungsten Carbide compact primary shielding for Small Medium Reactor Giménez, M.A.N.
2018
116 C p. 210-223
artikel
43 Virtual reality development and simulation of BMI nozzle inspection system for use during regular refueling outage of APR1400 family of reactors Abdallah, Khaled Atya Ahmed
2018
116 C p. 235-256
artikel
                             43 gevonden resultaten
 
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