Thermal-hydraulic tests of steam generator tube support plate /

Thermal-hydraulic tests of steam generator tube support plate /

Guardado en:

Detalles Bibliográficos
Autor principal:	Casell, D. S.
Otros Autores:	Vroom, D. W., Electric Power Research Institute.
Formato:	Libro
Lenguaje:
Publicado:	Palo Alto, Calf. : Electric Power Research Institute, 1983.
Colección:	EPRI. Final Report ; NP 2838 RP S121-1 (Jan. 1983)

Ejemplares similares

Analysis of single and two phase flow fields around PWR steam generator tube support plates /
Publicado: (c1979.)

THEDA-2 a multidimensional steam generator thermal hydraulic model /
por: Fortino, R. T.
Publicado: (1983.)

Thermal hydraulic analysis of the combustion engineering series 67 steam generator /
por: Inch, W. W. R.
Publicado: (1981.)

Integral experiments for PWR U-tube steam generators : part 1 : freon facility description and performance test results /
por: Adams, G.
Publicado: (1979.)

Loads on steam generator tubes during simulated loss-of-coolant accident conditions /
por: Guerrero, H. N.
Publicado: (1982.)

Loss-of-feed water transients in PWR U-tube steam generators : Simulation experiments and analysis /
por: Kalra, S. P.
Publicado: (1980.)

Steam its generation and use
por: Babcock-Wilcox.
Publicado: (c1922.)

Numerical methods for thermally expandable two-phase flow-computational techniques for steam generator modeling /
por: Hall, C. A.
Publicado: (1980.)

PWR steam generator cost benefit methodology : denting /
por: Rice, T. R.
Publicado: (1982.)

Calibrations of instrumented steam separators to determine quality and flow distribution in an operating steam generator /
por: Teigen, B. C.
Publicado: (1983.)

Simplified models for transient analysis of nuclear steam generators /
por: Lee, J. C.
Publicado: (1981.)

Thermal-hydraulics of nuclear reactors : papers presented at the Second International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Santa Barbara, California, USA, January 11-14, 1983 /
por: International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (2nd : 1983 : Santa Barbara, Calif.)
Publicado: (c1983.)

Thermal-hydraulic code qualification : ATHOS2 and data from BUGEY 4 and TRICASTIN 1 /
por: Masiello, P. J.
Publicado: (1983.)

Review of transient modeling of steam generator units in nuclear power plants /
por: Lee, J. C.
Publicado: (1980.)

The thermal hydraulics of a boiling water nuclear reactor /
por: Lahey, Richard T.
Publicado: (c1977.)

Methods for detailed thermal and hydraulic analysis of water cooled reactors /
por: Weisman, Joel.
Publicado: (1975.)

Steam : its generation and use with catalogue of the manufactures of the Babcock and Wilcox Company.

Eighth International Topical Meeting on Nuclear Reactor Thermal-Hydraulics : NURETH-8 : New horizons in nuclear reactor thermal-hydraulics : September 30-october 4, 1997, Kyoto, Japan /
por: International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (8th : 1997 : Kyoto, Japan)
Publicado: (1997?])

Electroless plating : fundamentals and applications /
Publicado: (c1990.)

Juan Plate : un pionero patagónico /
por: Hardt, Joaquín.
Publicado: (1992.)

Aeroelasticity of plates and shells /
por: Dowell, E. H.
Publicado: (1974.)

Ninth International Meeting on Nuclear Reactor Thermal Hydraulics : NURETH-9, San Francisco, USA, 3-8 october, 1999 /
Publicado: (2001.)

Análisis Post-Test de los ensayos experimentales realizados en el Oak Ridge National Laboratory thermal-hydraulic test facility utilizando RELAP5/MOD3 /
por: Di Césare, Julián.
Publicado: (2007.)

Plates to : the Middle East the Greek World and The Balkans to the Sixth Century B.C.. : The Cambridge Ancient History.
Publicado: (1984.)

Sixth International Topical Meeting on Nuclear reactor thermal hydraulics. : October 5-8, 1993 Grenoble, France : Selected Papers.
por: International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (6th : 1993 Oct. 5-8 : Grenoble, France)
Publicado: (1993.)

Chilling injury and yield of muskmelon grown with plastic mulches, rowcovers, and thermal water tubes
por: JENNI, Sylvie

Proceedings of the Fifth International Topical Meeting on Reactor Thermal Hydraulics, NURETH-5 : towards the next generation of nuclear power reactors, September 21-24, 1992, Little America Hotel, Salt Lake City, UT, USA /
por: International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (5th : 1992 : Salt Lake City, Utah)
Publicado: (c1992-)

Theory and design of plate and shell structures /
por: Jawad, Maan H.
Publicado: (1994.)

Steam boilers
por: Croft, Terrel
Publicado: (1937.)

From generation to generation.
por: Eisenstadt, S:N.
Publicado: (1956.)

Selected papers from the Third International Topical Meeting on Nuclear Reactor Thermal-Hydraulics : October 1985, Newport, Rhode Island, USA.
por: International Topical Meeting on Reactor Thermal Hydraulics (3rd : 1985 : Newport, R.I.)
Publicado: (1987.)

Limit analysis of rotationally symmetric plates and shells
por: Hodge, Philip G.
Publicado: (1963.)

Selected papers from the Third International Topical Meeting on Nuclear Reactor Thermal-Hydraulics & Operations : Seoul, Korea, November 1988.
por: International Topical Meeting on Nuclear Reactor Thermal-Hydraulics & Operations (3rd : 1988 : Seoul, Korea)
Publicado: (1990.)

Transmitting tubes
por: Philips.
Publicado: (19-??.)

Vacuum tubes /
por: Spangenberg, Karl R.
Publicado: (1948.)

Steam power stations
por: Gaffert, Gustaf A.
Publicado: (1952.)

RAILROADS. IN THE DAYS OF STEAM

Hydraulic measurements
por: Addison, Herbert
Publicado: (1941.)

Hydraulic fracturing
por: Gidley, John L.
Publicado: (1969.)

Hydraulic fracturing
por: Howard, George C.
Publicado: (c1970.)