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A three-dimensional transient model for EGS subsurface thermohydraulic processFANGMING JIANG; JILIANG CHEN; WENBO HUANG et al.Energy (Oxford). 2014, Vol 72, pp 300-310, issn 0360-5442, 11 p.Article
Précision sur la méthode de calcul des processus hydraulique et thermique dans les surchauffeurs de vapeur des chaudières puissantesCHEBUNAEV, V. V; LOKSHIN, V. A; VUKOLOVA, A. I et al.Ènergomašinostroenie. 1988, Num 3, pp 23-29, issn 0131-1336Article
Understanding by seeing: Thermal hydraulics using a glass model of a pressurised water reactorSEEWALD, Michael.VGB powertech. 2013, Num 5, issn 1435-3199, 6-7, 33-36 [6 p.]Article
International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH)PODOWSKI, Michael Z.Nuclear engineering and design. 1997, Vol 177, Num 1-3, issn 0029-5493, 374 p.Conference Proceedings
Monte Carlo departure from nucleate boiling ratio limit development using few-channel thermal-hydraulics code modelsANDERSON, R. C; BASEHORE, K. L.Nuclear technology. 1987, Vol 77, Num 2, pp 227-230, issn 0029-5450Article
The pseudocritical regions for supercritical waterIMRE, A. R; DEITERS, U. K; KRASKA, T et al.Nuclear engineering and design. 2012, Vol 252, pp 179-183, issn 0029-5493, 5 p.Article
Analysis of the Chernobyl accident from 1:19:00 to the first power excursionMOCHIZUKI, Hiroyasu.Nuclear engineering and design. 2007, Vol 237, Num 3, pp 300-307, issn 0029-5493, 8 p.Article
Tecnologie informatiche, telecomunicazioni e l'impresa termoidraulica = Telecommunication and information technologies in the field of thermohydraulicsRHO, R.Installatore italiano. 1999, Vol 50, Num 8, pp 41-48, issn 0020-2118Article
Thermohydraulique de la zone non saturée en relation avec les échanges sol-atmosphèreBRUNET, Y; VAUCLIN, M; VACHAUD, G et al.Houille blanche (Grenoble). 1985, Num 3-4, pp 227-238, issn 0018-6368Article
Uncertainty evaluation of simulation of E-108 test facility experimentsURBONAS, Rolandas.International heat transfer conference. 2002, pp 639-644, isbn 2-84299-308-X, 6 p.Conference Paper
Joint + conductor thermal-hydraulic experiment and analysis on the Full size joint Sample using MITHRANDIR 2.1ZANINO, R; SANTAGATI, P; SAVOLDI, L et al.IEEE transactions on applied superconductivity. 2000, Vol 10, Num 1, pp 1110-1113, issn 1051-8223Conference Paper
Lead―bismuth eutectic technology for Hyperion reactorZHANG, J; KAPERNICK, R. J; MCCLURE, P. R et al.Journal of nuclear materials. 2013, Vol 441, Num 1-3, pp 644-649, issn 0022-3115, 6 p.Conference Paper
Development and assessment of system analysis code, TASS/SMR for integral reactor, SMARTCHUNG, Y. J; JUN, I. S; KIM, S. H et al.Nuclear engineering and design. 2012, Vol 244, pp 52-60, issn 0029-5493, 9 p.Article
Thermal and thermohydraulic performance evaluation of a novel type double pass packed bed solar air heater under external recycle using an analytical and RSM (response surface methodology) combined approachSINGH, Satyender; DHIMAN, Prashant.Energy (Oxford). 2014, Vol 72, pp 344-359, issn 0360-5442, 16 p.Article
State space model extraction of thermohydraulic systems ― Part II: A linear graph approach applied to a Brayton cycle-based power conversion unitUREN, Kenneth Richard; VAN SCHOOR, George.Energy (Oxford). 2013, Vol 61, pp 381-396, issn 0360-5442, 16 p.Article
Compound waves in a thermohydrodynamic lattice BGK scheme using non-perturbative equilibriaDELLAR, P. J.Europhysics letters (Print). 2002, Vol 57, Num 5, pp 690-696, issn 0295-5075Article
Post critical heat transfer predictions using a modified RELAP5/MOD2 computer codeHASSAN, Y. A.Nuclear science and engineering. 1989, Vol 103, Num 1, pp 70-80, issn 0029-5639, 11 p.Article
Modeling and loss-of-coolant accident analysis of a nuclear power plant using RELAP5/MOD2SALIM, P; HASSAN, Y. A.Nuclear technology. 1990, Vol 90, Num 3, pp 275-285, issn 0029-5450, 11 p.Article
Coupling codes including deformation exchange suitable for non conforming and unstructured large meshesDUPLEX, B; GRANDOTTO, M; PERDU, F et al.Nuclear engineering and design. 2012, Vol 253, pp 60-70, issn 0029-5493, 11 p.Article
A diagnostic system for identifying accident conditions in a nuclear reactorSANTHOSH, T. V; KUMAR, M; LELE, H. G et al.Nuclear engineering and design. 2011, Vol 241, Num 1, pp 177-184, issn 0029-5493, 8 p.Article
Experimental study of forced convection heat transfer from a cam shaped tube in cross flowsNOURI-BORUIERDI, A; LAVASANI, A. M.International journal of heat and mass transfer. 2007, Vol 50, Num 13-14, pp 2605-2611, issn 0017-9310, 7 p.Article
Simulation of reactivity transients in a miniature neutron source reactor coreAKAHO, E. H. K; MAAKUU, B. T.Nuclear engineering and design. 2002, Vol 213, Num 1, pp 31-42, issn 0029-5493Article
Experimental and numerical investigation of thermal-hydraulic characteristics of a wavy-channel compact heat exchangerMULEY, Arun; BORGHESE, Joseph B; MANGLIK, Raj M et al.International heat transfer conference. 2002, pp 417-422, isbn 2-84299-308-X, 6 p.Conference Paper
BR2 reactor core steady state and transient modelingMAKARENKO, A; PETROVA, T.International topical meeting on research reactor fuel management. 2000, pp 111-115Conference Paper
Thoughts on the early days of the BNL reactor theory groupAUERBACH, T; MICHAEL, P; ROTHENSTEIN, W et al.Progress in nuclear energy (New series). 1999, Vol 34, Num 4, pp 313-335, issn 0149-1970Article