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                             40 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Accident management following loss of residual heat removal during mid-loop operation in a Westinghouse two-loop PWR Birchley, J.
2008
238 9 p. 2173-2181
9 p.
artikel
2 A comparative neutronic study of the standard HEU core and various potential LEU alternatives for a typical MNSR system Waqar, Sadaf
2008
238 9 p. 2302-2307
6 p.
artikel
3 A heat transfer analysis of the CCI experiments 1–3 Sevón, Tuomo
2008
238 9 p. 2377-2386
10 p.
artikel
4 A model based on bootstrapped neural networks for computing the maximum fuel cladding temperature in an Rmbk-1500 nuclear reactor accident Cadini, F.
2008
238 9 p. 2165-2172
8 p.
artikel
5 Application of mechanistic criteria of cladding oxide shell failure to the analysis of core degradation simulated in bundle meltdown tests Veshchunov, M.S.
2008
238 9 p. 2219-2229
11 p.
artikel
6 A simple approach to the prediction of waterhammer transients in a pipe line with entrapped air Epstein, Michael
2008
238 9 p. 2182-2188
7 p.
artikel
7 A simple probabilistic approach to evaluate radioiodine behavior at severe accidents: Application to PHEBUS test FPT1 Rýdl, Adolf
2008
238 9 p. 2387-2391
5 p.
artikel
8 A study on the evolution of crack networks under thermal fatigue loading Kamaya, Masayuki
2008
238 9 p. 2147-2154
8 p.
artikel
9 A two-phase methodology to predict FAC wear sites in the piping system of a BWR Ferng, Yuh Ming
2008
238 9 p. 2189-2196
8 p.
artikel
10 Corrigendum to “Novel porous media formulation for multiphase flow conservation equations” [Nucl. Eng. Des. 237 (2007) 918–942] Sha, W.T.
2008
238 9 p. 2494-
1 p.
artikel
11 Experimental and theoretical study on transition boiling concerning downward-facing horizontal surface in confined space Zhao, D.W.
2008
238 9 p. 2460-2467
8 p.
artikel
12 Failure characteristics of cladding tubes under RIA conditions Leclercq, Sylvain
2008
238 9 p. 2206-2218
13 p.
artikel
13 Finite element analysis of the optimized H type grid spring by using gap elements Kim, Kang Soo
2008
238 9 p. 2239-2244
6 p.
artikel
14 Functional reliability analysis of Safety Grade Decay Heat Removal System of Indian 500MWe PFBR Mathews, T. Sajith
2008
238 9 p. 2369-2376
8 p.
artikel
15 Heat transfer in two-component internal mist cooling Novak, V.
2008
238 9 p. 2341-2350
10 p.
artikel
16 Heat transfer in two-component internal mist cooling Novak, V.
2008
238 9 p. 2351-2358
8 p.
artikel
17 Homogenisation method for the dynamic analysis of a complete nuclear steam generator with fluid–structure interaction Sigrist, Jean-François
2008
238 9 p. 2261-2271
11 p.
artikel
18 Incipient fault detection of motor-operated valves using wavelet transform analysis Carneiro, Alvaro Luiz Guimarães
2008
238 9 p. 2453-2459
7 p.
artikel
19 Insights from fire PSA for enhancing NPP safety Vinod, Gopika
2008
238 9 p. 2359-2368
10 p.
artikel
20 Integrating Safety Critical Software System in Probabilistic Safety Assessment Vinod, Gopika
2008
238 9 p. 2392-2399
8 p.
artikel
21 Limit load solutions of thick-walled cylinders with fully circumferential cracks under combined internal pressure and axial tension Gao, Zengliang
2008
238 9 p. 2155-2164
10 p.
artikel
22 Methods for the evaluation and synthesis of multiple sources of information applied to nuclear computer codes Destercke, S.
2008
238 9 p. 2484-2493
10 p.
artikel
23 Modelling of PWR lower head failure under severe accident loading using improved shells of revolution theory Koundy, Vincent
2008
238 9 p. 2400-2410
11 p.
artikel
24 New capabilities of simulating fission product transport in circuits with ASTEC/SOPHAEROS v.1.3 Cousin, F.
2008
238 9 p. 2430-2438
9 p.
artikel
25 Nuclear powered heat pumps for near-term process heat applications Marmier, A.
2008
238 9 p. 2272-2284
13 p.
artikel
26 Power peakings in mixed TRIGA cores Snoj, Luka
2008
238 9 p. 2473-2479
7 p.
artikel
27 Progress on PWR lower head failure predictive models Koundy, Vincent
2008
238 9 p. 2420-2429
10 p.
artikel
28 Scaling methodology for a reduced-height reduced-pressure integral test facility to investigate direct vessel injection line break SBLOCA Bae, Byoung Uhn
2008
238 9 p. 2197-2205
9 p.
artikel
29 Shape optimization of a perforated pressure vessel cover under linearized stress constraints Choi, Woo-Seok
2008
238 9 p. 2468-2472
5 p.
artikel
30 Solution of neutron transport equation using Daubechies’ wavelet expansion in the angular discretization Cao, Liangzhi
2008
238 9 p. 2292-2301
10 p.
artikel
31 Space reactor power systems with no single point failures El-Genk, Mohamed S.
2008
238 9 p. 2245-2255
11 p.
artikel
32 Study of tearing behaviour of a PWR reactor pressure vessel lower head under severe accident loadings Koundy, Vincent
2008
238 9 p. 2411-2419
9 p.
artikel
33 The modeling of graphite oxidation behavior for HTGR fuel coolant channels under normal operating conditions Yu, Xinli
2008
238 9 p. 2230-2238
9 p.
artikel
34 Theoretical modeling of condensation of steam outside different vertical geometries (tube, flat plates) in the presence of noncondensable gases like air and helium Ganguli, Arijit
2008
238 9 p. 2328-2340
13 p.
artikel
35 Thermal hydraulic effect of fuel plate surface roughness Guillen, Donna Post
2008
238 9 p. 2480-2483
4 p.
artikel
36 Transmission probability method for solving neutron transport equation in three-dimensional triangular-z geometry Liu, Guoming
2008
238 9 p. 2285-2291
7 p.
artikel
37 Uncertainties of creep model in stress analysis and life prediction of graphite component Wang, Haitao
2008
238 9 p. 2256-2260
5 p.
artikel
38 Validation of the sub-channel code F-COBRA-TF Glück, M.
2008
238 9 p. 2317-2327
11 p.
artikel
39 Validation of the sub-channel code F-COBRA-TF Glück, M.
2008
238 9 p. 2308-2316
9 p.
artikel
40 Vibration-based diagnosis techniques used in nuclear power plants: An overview of experiences Sinha, Jyoti K.
2008
238 9 p. 2439-2452
14 p.
artikel
                             40 gevonden resultaten
 
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