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 |