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                             40 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A design of human–machine interface for the two-modular high-temperature gas-cooled reactor nuclear power plant Jia, Qianqian
 2014
 77 C p. 336-343
8 p.
 artikel
2 Analysis of flow frictional resistance in U-tubes under ocean conditions Chu, Xi
 2014
 77 C p. 194-200
7 p.
 artikel
3 Analysis of ITU TRIGA Mark II research reactor using Monte Carlo method Türkmen, Mehmet
 2014
 77 C p. 152-159
8 p.
 artikel
4 Analysis of measures to enhance safeguards, and proliferation resistance in thorium based fuel fabrication plants Gangotra, Suresh
 2014
 77 C p. 20-31
12 p.
 artikel
5 Analysis of PWR RPV lower head SBLOCA scenarios with the failure of high-pressure injection system using MAAP5 Li, Wei
 2014
 77 C p. 48-64
17 p.
 artikel
6 An Autonomous Reactivity Control system for improved fast reactor safety Qvist, Staffan
 2014
 77 C p. 32-47
16 p.
 artikel
7 A novel mathematical model for two-energy groups of the point kinetics reactor dynamics Aboanber, Ahmed E.
 2014
 77 C p. 160-166
7 p.
 artikel
8 A point kinetics model of the Y12 accident Zamacinski, T.
 2014
 77 C p. 92-106
15 p.
 artikel
9 Application of dynamic probabilistic risk assessment techniques for uncertainty quantification in generation IV reactors Vierow, K.
 2014
 77 C p. 320-328
9 p.
 artikel
10 APSTRACT: Development and validation of sensitivity analysis code Lüley, Jakub
 2014
 77 C p. 124-131
8 p.
 artikel
11 Assessment of CFD for the Canadian SCWR bundle with wire wraps Podila, K.
 2014
 77 C p. 373-380
8 p.
 artikel
12 A summary of sodium-cooled fast reactor development Aoto, Kazumi
 2014
 77 C p. 247-265
19 p.
 artikel
13 Causal relationship between nuclear energy consumption and economic growth in G6 countries: Evidence from panel Granger causality tests Chang, T.
 2014
 77 C p. 187-193
7 p.
 artikel
14 Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology Scarlat, Raluca O.
 2014
 77 C p. 406-420
15 p.
 artikel
15 Design of serpentine cask for Ghana research reactor-1 spent nuclear fuel Abrefah, R.G.
 2014
 77 C p. 84-91
8 p.
 artikel
16 Development of CUPID-SG for the analysis of two-phase flows in PWR steam generators Kim, Hyungrae
 2014
 77 C p. 132-140
9 p.
 artikel
17 Editorial Board 2014
 77 C p. IFC-
1 p.
 artikel
18 Experimental and theoretical analysis of bubble departure behavior in narrow rectangular channel Xu, JianJun
 2014
 77 C p. 1-10
10 p.
 artikel
19 Experimental study of water film flow on large vertical and inclined flat plate Yu, Y.Q.
 2014
 77 C p. 176-186
11 p.
 artikel
20 Generation IV International Forum: A decade of progress through international cooperation Kelly, John E.
 2014
 77 C p. 240-246
7 p.
 artikel
21 Investigations on coupled code PWR simulations using COBRA-TF with soluble boron tracking model Biery, M.
 2014
 77 C p. 72-83
12 p.
 artikel
22 Lumped-parameter simulations of wall condensation and sump evaporation under typical thermal-hydraulic conditions of nuclear reactor containment severe accident Malet, J.
 2014
 77 C p. 11-19
9 p.
 artikel
23 MAAP5 simulation of the PWR severe accident induced by pressurizer safety valve stuck-open accident Li, Longze
 2014
 77 C p. 141-151
11 p.
 artikel
24 Media coverage and government policy of nuclear power in the People's Republic of China Wang, Yongxiang
 2014
 77 C p. 214-223
10 p.
 artikel
25 Overview and progress in the European project: “Supercritical Water Reactor – Fuel Qualification Test” Ruzickova, M.
 2014
 77 C p. 381-389
9 p.
 artikel
26 Overview of lead-cooled fast reactor activities Alemberti, Alessandro
 2014
 77 C p. 300-307
8 p.
 artikel
27 Phenomenology, methods and experimental program for fluoride-salt-cooled, high-temperature reactors (FHRs) Zweibaum, Nicolas
 2014
 77 C p. 390-405
16 p.
 artikel
28 Preface McFarlane, Harold
 2014
 77 C p. 239-
1 p.
 artikel
29 Research on active magnetic bearing applied in Chinese modular high-temperature gas-cooled reactor Yang, Guojun
 2014
 77 C p. 352-360
9 p.
 artikel
30 Review of R&D for supercritical water cooled reactors Schulenberg, Thomas
 2014
 77 C p. 282-299
18 p.
 artikel
31 Status of the very high temperature reactor system Fütterer, Michael A.
 2014
 77 C p. 266-281
16 p.
 artikel
32 Study on pressure relief system design for high temperature gas cooled reactor Yan, Wang
 2014
 77 C p. 344-351
8 p.
 artikel
33 Study the neutronic analysis and burnup for BWR fueled with hydride fuel using MCNPX code Galahom, A. Abdelghafar
 2014
 77 C p. 65-71
7 p.
 artikel
34 Supercritical water-cooled reactor materials – Summary of research and open issues Guzonas, D.
 2014
 77 C p. 361-372
12 p.
 artikel
35 Technology and policy issues relating to future developments in research and radioisotope production reactors Nuttall, William J.
 2014
 77 C p. 201-213
13 p.
 artikel
36 The design and thermohydraulics study of the HTR-10 High Temperature Helium Experimental Loop Yang, Chen
 2014
 77 C p. 329-335
7 p.
 artikel
37 The molten salt reactor (MSR) in generation IV: Overview and perspectives Serp, Jérôme
 2014
 77 C p. 308-319
12 p.
 artikel
38 Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors Lindley, Benjamin A.
 2014
 77 C p. 107-123
17 p.
 artikel
39 Two-phase flow measurements at high void fraction by a Venturi meter Monni, Grazia
 2014
 77 C p. 167-175
9 p.
 artikel
40 Use of TRACE best estimate code to analyze spent fuel storage pools safety Carlos, S.
 2014
 77 C p. 224-238
15 p.
 artikel
                             40 gevonden resultaten
 
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