Diseño Conceptual de DuCom : un nuevo concepto de centrales híbridas gas-nuclear de ciclo dual combinado /

Diseño Conceptual de DuCom : un nuevo concepto de centrales híbridas gas-nuclear de ciclo dual combinado /

Guardado en:

Detalles Bibliográficos
Autor principal:	Kyung, Kyu-Hyung.
Otros Autores:	Florido, Pablo C., Universidad Nacional de Cuyo. Instituto Balseiro.
Formato:	Libro
Lenguaje:	Español
Publicado:	2000.
Materias:	Reactors > Theses. Nuclear fuels > Theses. Reactores > Tesis.

Ejemplares similares

The linear reactivity model for nuclear fuel management /
por: Driscoll, M. J.
Publicado: (c1990.)

Management of spent fuel from nuclear power reactors proceedings of an International Conference /
por: International Conference on Management of spent fuel from nuclear power reactors (31 May-4 June 2010 : Vienna, Austria)
Publicado: (2015.)

Les combustibles nucléaires /
por: Sauteron, Jean.
Publicado: ([1965])

Desarrollo del árbol de eventos del grupo T13 "pérdida del condensador", luego de las modificaciones a la instalación para la Central Nuclear Atucha 1. /
por: Khatchikian, Facundo Andrés.
Publicado: (2000.)

Reactor core fuel management /
por: Silvennoinen, P.
Publicado: (1976.)

Proceedings, ANS topical meeting, Reactor Safety Aspects of Fuel Behavior, August 2-6, 1981, Sun Valley, Idaho.
Publicado: (c1981.)

Engineering for nuclear fuel reprocessing /
por: Long, Justin T.
Publicado: (c1978.)

Status and advances in MOX fuel technology /
Publicado: (2003.)

Diseño conceptual del CAREM-Plus /
por: Rubiolo, Pablo R.
Publicado: (1996.)

Proceedings of Specialist Meeting on the Behaviour of Water Reactor Fuel Elements Under Accident Conditions, Spåtind, Norway, 13-16 September 1976 /
por: Specialist Meeting on the Behaviour of Water Reactor Fuel Elements Under Accident Conditions (1976 : Spåtind, Norway)
Publicado: ([1977])

Diseño conceptual de un reactor nuclear compacto /
por: Giménez, Juan Bautista E.
Publicado: (2016.)

Centros regionales para el ciclo del combustible nuclear : Síntesis del informe sobre el proyecto de estudio del OIEA. /
Publicado: (1977.)

Research reactor fuel management international meetings (RRFM) : 1997-2004 /
Publicado: (2004.)

Topical meeting proceedings, Monterey, California, March 5-8, 1979 /
por: International Conference on Fast Breeder Reactor Fuel Performance (1979 : Monterey, Calif.)
Publicado: (c1979.)

Country nuclear fuel cycle profiles /
Publicado: (2005.)

Regional nuclear fuel cycle centers : 1977 report of the IAEA study project.
Publicado: (1977.)

Executive Conference on Spent Fuel Policy and Its Implications, Pineisle Resort, Buford, Georgia, April 2-5, 1978 : Executive Conference proceedings.
por: Executive Conference on Spent Fuel Policy and Its Implications (1978 : Buford, Ga.)
Publicado: (c1978.)

Review of fuel element developments for cooled nuclear power reactors /
Publicado: (1989.)

Storage of reactor spent fuel in water pools : survey of World Experience /
Publicado: (1982.)

Modernización de la lógica de control del sistema de localización de elementos combustibles fallados de la Central Nuclear Embalse /
por: Calderón, Darío A.
Publicado: (2004.)

Trabajo especial de física /
por: Farkas, Diana.
Publicado: (1975.)

The nuclear fuel cycle information system : a directory of nuclear fuel cycle facilities.
Publicado: (1987-)

Proceedings /
por: Conference on Fast Reactor Fuel Element Technology (1971 : New Orleans, La.)
Publicado: ([c1971])

Improvements in water reactor fuel technology and utilization : proceedings of an International Symposium on Improvements in Water Reactor Fuel Technology and Utilization /
por: International Symposium on Improvements in Water Reactor Fuel Technology and Utilization (1986 : Stockholm, Sweden)
Publicado: (1987.)

Fast reactor fuel and fuel elements ; proceedings /
por: International Meeting on Fast Reactor and Fuel Elements (1970 : Karlsruhe)
Publicado: (1970.)

The radiological accident in the reprocessing plant at Tomsk.
Publicado: (1998.)

Light water reactor nuclear fuel cycle /
Publicado: (c1981.)

Corrosion of research reactor aluminium clad spent fuel in water /
Publicado: (2003.)

Nuclear safety 1975 : proceedings of the American Nuclear Society, National Topical Meeting, October 6-8, 1975, Tucson, Arizona /
Publicado: (1975.)

Back end of the nuclear fuel cycle : strategies and options : proceedings of an International Symposium on the Back End of the Nuclear Fuel Cycle, Strategies and Options /
por: International Symposium on the Back End of the Nuclear Fuel Cycle : (1987 : Vienna, Austria)
Publicado: (1987.)

Options, experience, and trends in spent nuclear fuel management /
Publicado: (1995.)

Safe enclosure of nuclear facilities during deferred dismantling /
Publicado: (2002.)

Código de cálculo neutrónico CONDOR para la resolución de elementos combustibles nucleares /
por: Villarino, Eduardo A.
Publicado: (1992.)

Ingeniería de reactores nucleares /
por: Glasstone, Samuel, 1897-
Publicado: (1968-1975.)

Reactor burn-up physics /
por: Panel on Reactor Burn-up Physics (1971 : Vienna)
Publicado: (1973.)

Plutonium, power, and politics : international arrangements for the disposition of spent nuclear fuel /
por: Rochlin, Gene I.
Publicado: (c1979.)

Fuel and fuel elements for fast reactors ; proceedings of a Symposium .. /
por: Symposium on Fuel and Fuel Elements for Fast Reactors (1973 : Brussels)
Publicado: (1974.)

Nuclear reactors /
Publicado: (1960.)

Nuclear reactor engineering /
por: Glasstone, Samuel, 1897-1986.
Publicado: (1994.)

Material science in nuclear technology /
por: Kummerer, K. R.
Publicado: (1982.)