Finite element analysis of the optimized H type grid spring by using gap elements (Unknown)
- New search for: Kim, Kang Soo
- New search for: Kim, Kang Soo
- New search for: Yoon, Kyung Ho
- New search for: Song, Kee Nam
- New search for: Park, Keun Bae
In:
Nuclear engineering and design
;
238
, 9
; 2239-2244
;
2008
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ISSN:
- Article (Journal) / Print
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Title:Finite element analysis of the optimized H type grid spring by using gap elements
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Contributors:
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Published in:Nuclear engineering and design ; 238, 9 ; 2239-2244
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Publisher:
- New search for: North-Holland Publ. Co.
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Place of publication:Amsterdam
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Publication date:2008
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ISSN:
-
ZDBID:
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Type of media:Article (Journal)
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Type of material:Print
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Language:Unknown
- New search for: 52.55
- Further information on Basic classification
- New search for: 535/5540
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Keywords:
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Classification:
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Source:
Table of contents – Volume 238, Issue 9
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 2147
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A study on the evolution of crack networks under thermal fatigue loadingKamaya, Masayuki / Taheri, Said et al. | 2008
- 2155
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Limit load solutions of thick-walled cylinders with fully circumferential cracks under combined internal pressure and axial tensionGao, Zengliang / Cai, Gangsi / Liang, Lihua / Lei, Yuebao et al. | 2008
- 2165
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A model based on bootstrapped neural networks for computing the maximum fuel cladding temperature in an Rmbk-1500 nuclear reactor accidentCadini, F. / Zio, E. / Kopustinskas, V. / Urbonas, R. et al. | 2008
- 2173
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Accident management following loss of residual heat removal during mid-loop operation in a Westinghouse two-loop PWRBirchley, J. / Haste, T.J. / Richner, M. et al. | 2008
- 2182
-
A simple approach to the prediction of waterhammer transients in a pipe line with entrapped airEpstein, Michael et al. | 2008
- 2189
-
A two-phase methodology to predict FAC wear sites in the piping system of a BWRFerng, Yuh Ming / Tseng, Yung Shin / Pei, Bau Shei / Wang, S. Long et al. | 2008
- 2197
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Scaling methodology for a reduced-height reduced-pressure integral test facility to investigate direct vessel injection line break SBLOCABae, Byoung Uhn / Lee, Keo Hyoung / Kim, Yong Soo / Yun, Byong Jo / Park, Goon Cherl et al. | 2008
- 2206
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Failure characteristics of cladding tubes under RIA conditionsLeclercq, Sylvain / Parrot, Aurore / Leroy, Maurice et al. | 2008
- 2219
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Application of mechanistic criteria of cladding oxide shell failure to the analysis of core degradation simulated in bundle meltdown testsVeshchunov, M.S. / Boldyrev, A.V. / Toth, B. et al. | 2008
- 2230
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The modeling of graphite oxidation behavior for HTGR fuel coolant channels under normal operating conditionsYu, Xinli / Brissonneau, Laurent / Bourdeloie, Christian / Yu, Suyuan et al. | 2008
- 2239
-
Finite element analysis of the optimized H type grid spring by using gap elementsKim, Kang Soo / Yoon, Kyung Ho / Song, Kee Nam / Park, Keun Bae et al. | 2008
- 2245
-
Space reactor power systems with no single point failuresEl-Genk, Mohamed S. et al. | 2008
- 2256
-
Uncertainties of creep model in stress analysis and life prediction of graphite componentWang, Haitao / Yu, Suyuan et al. | 2008
- 2261
-
Homogenisation method for the dynamic analysis of a complete nuclear steam generator with fluid–structure interactionSigrist, Jean-François / Broc, Daniel et al. | 2008
- 2272
-
Nuclear powered heat pumps for near-term process heat applicationsMarmier, A. / Fütterer, M.A. et al. | 2008
- 2285
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Transmission probability method for solving neutron transport equation in three-dimensional triangular-z geometryLiu, Guoming / Wu, Hongchun / Cao, Liangzhi et al. | 2008
- 2292
-
Solution of neutron transport equation using Daubechies’ wavelet expansion in the angular discretizationCao, Liangzhi / Wu, Hongchun / Zheng, Youqi et al. | 2008
- 2302
-
A comparative neutronic study of the standard HEU core and various potential LEU alternatives for a typical MNSR systemWaqar, Sadaf / Mirza, Sikander M. / Mirza, Nasir M. / Asad, Tariq et al. | 2008
- 2308
-
Validation of the sub-channel code F-COBRA-TFGlück, M. et al. | 2008
- 2308
-
Validation of the sub-channel code F-COBRA-TF:Part I. Recalculation of single-phase and two-phase pressure loss measurementsGluck, M. et al. | 2008
- 2317
-
Validation of the sub-channel code F-COBRA-TF:Part II. Recalculation of void measurementsGluck, M. et al. | 2008
- 2328
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Theoretical modeling of condensation of steam outside different vertical geometries (tube, flat plates) in the presence of noncondensable gases like air and heliumGanguli, Arijit / Patel, A.G. / Maheshwari, N.K. / Pandit, A.B. et al. | 2008
- 2341
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Heat transfer in two-component internal mist coolingNovak, V. / Sadowski, D.L. / Schoonover, K.G. / Abdel-Khalik, S.I. / Ghiaasiaan, S.M. et al. | 2008
- 2341
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Heat transfer in two-component internal mist cooling:Part I. Experimental investigationNovak, V. / Sadowski, D. L. / Schoonover, K. G. / Abdel-Khalik, S. I. / Ghiaasiaan, S. M. et al. | 2008
- 2351
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Heat transfer in two-component internal mist cooling:Part II. Mechanistic modelingNovak, V. / Sadowski, D. L. / Schoonover, K. G. / Shin, S. / Abdel-Khalik, S. I. / Ghiaasiaan, S. M. et al. | 2008
- 2359
-
Insights from fire PSA for enhancing NPP safetyVinod, Gopika / Saraf, R.K. / Ghosh, A.K. / Kushwaha, H.S. / Sharma, P.K. et al. | 2008
- 2369
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Functional reliability analysis of Safety Grade Decay Heat Removal System of Indian 500MWe PFBRMathews, T. Sajith / Ramakrishnan, M. / Parthasarathy, U. / Arul, A. John / Kumar, C. Senthil et al. | 2008
- 2377
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A heat transfer analysis of the CCI experiments 1–3Sevón, Tuomo et al. | 2008
- 2387
-
A simple probabilistic approach to evaluate radioiodine behavior at severe accidents: Application to PHEBUS test FPT1Rýdl, Adolf et al. | 2008
- 2392
-
Integrating Safety Critical Software System in Probabilistic Safety AssessmentVinod, Gopika / Santosh, T.V. / Saraf, R.K. / Ghosh, A.K. et al. | 2008
- 2400
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Modelling of PWR lower head failure under severe accident loading using improved shells of revolution theoryKoundy, Vincent / Hoang, Nguyen Hieu et al. | 2008
- 2411
-
Study of tearing behaviour of a PWR reactor pressure vessel lower head under severe accident loadingsKoundy, Vincent / Caroli, Cataldo / Nicolas, Laetitia / Matheron, Philippe / Gentzbittel, Jean-Marie / Coret, Michel et al. | 2008
- 2420
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Progress on PWR lower head failure predictive modelsKoundy, Vincent / Fichot, Florian / Willschuetz, Hans-Georg / Altstadt, Eberhard / Nicolas, Laetitia / Lamy, Jean-Sylvestre / Flandi, Laila et al. | 2008
- 2430
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New capabilities of simulating fission product transport in circuits with ASTEC/SOPHAEROS v.1.3Cousin, F. / Dieschbourg, K. / Jacq, F. et al. | 2008
- 2439
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Vibration-based diagnosis techniques used in nuclear power plants: An overview of experiencesSinha, Jyoti K. et al. | 2008
- 2453
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Incipient fault detection of motor-operated valves using wavelet transform analysisCarneiro, Alvaro Luiz Guimarães / Silva, Aucyone Augusto da / Upadhyaya, Belle R. et al. | 2008
- 2460
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Experimental and theoretical study on transition boiling concerning downward-facing horizontal surface in confined spaceZhao, D.W. / Su, G.H. / Tian, W.X. / Sugiyama, K. / Qiu, S.Z. et al. | 2008
- 2468
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Shape optimization of a perforated pressure vessel cover under linearized stress constraintsChoi, Woo-Seok / Kim, Tae-Wan / Seo, Ki-Seog et al. | 2008
- 2473
-
Power peakings in mixed TRIGA coresSnoj, Luka / Ravnik, Matjaž et al. | 2008
- 2480
-
Thermal hydraulic effect of fuel plate surface roughnessGuillen, Donna Post / Yoder, Timothy S. et al. | 2008
- 2484
-
Methods for the evaluation and synthesis of multiple sources of information applied to nuclear computer codesDestercke, S. / Chojnacki, E. et al. | 2008
- 2494
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Corrigendum to “Novel porous media formulation for multiphase flow conservation equations” [Nucl. Eng. Des. 237 (2007) 918–942]Sha, W.T. / Chao, B.T. et al. | 2007