Evaluación de la distribución del flujo azimutal en el recipiente de presión de Atucha I /

Evaluación de la distribución del flujo azimutal en el recipiente de presión de Atucha I /

Guardado en:

Detalles Bibliográficos
Autor principal:	Ferraro, Diego.
Otros Autores:	Blaumann, Herman., Longhino, Juan., Universidad Nacional de Cuyo. Instituto Balseiro
Formato:	Libro
Lenguaje:	Español
Publicado:	2008.
Materias:	Nuclear power plants > Theses. Pressure vessels > Theses. Irradiation > Theses. Dosimetry > Theses. Damage > Theses. Centrales nucleares > Tesis. Vasijas de presión > Tesis. Irradiación > Tesis. Dosimetría > Tesis. Daño > Tesis.
Acceso en línea:	Indice.

Ejemplares similares

Guidelines for application of the master curve approach to reactor pressure vessel integrity in nuclear power plants /
Publicado: (2005.)

Recurring inspection of nuclear reactor steel pressure vessels : Report of a Panel ... held in Pilsen, Czechoslovak Socialist Republic, 3-7 Oct. 1966.
por: Panel on Recurring Inspection of Nuclear Reactor Steel Pressure Vessels (1966 : Plze´n)
Publicado: (1968.)

Pressure vessel codes : their application to nuclear reactor systems /
Publicado: (1966.)

Symposium on Seismic Analysis of Pressure Vessel and Piping Components ; presentations from ASME First National Congress on Pressure Vessels and Piping, San Francisco, California, May 1971 /
por: Symposium on Seismic Analysis of Pressure Vessel and Piping Components (1971 : San Francisco, Calif.)
Publicado: ([1971])

Reliability of reactor pressure components : proceedings of an International Symposium on Reliability of Reactor Pressure Components /
por: International Symposium on Reliability of Reactor Pressure Components (1983 : Stuttgart, Germany)
Publicado: (1983.)

Design and analysis of ASME boiler and pressure vessel components in the creep range /
Publicado: (c2009.)

Recurring inspection of nuclear reactor steel pressure vessels /
Publicado: (1968.)

Guidebook for the design of ASME section VIII pressure vessels /
por: Farr, James R.
Publicado: (c2010.)

Seventh German-Japanese Seminar : GJS 97 : Stuttgart, Germany, 29-30 September 1997 /
por: German-Japanese Seminar (7th : 1997 : Stuttgart, Germany)
Publicado: (2000.)

Análisis determinísticos y probabilísticos de la resistencia estructural de recipientes de contención de acero /
por: Sánchez Sarmiento, Gustavo.
Publicado: (1996.)

Neutron irradiation embrittlement of reactor pressure vessel steels /
por: Steele, L. E. 1928-
Publicado: (1975.)

Reliability problems of reactor pressure components : proceedings of a Symposium on ... organized by the International Atomic Energy Agency and held in Vienna, 10-13 Oct. 1977.
por: Symposium on Application of Reliability Technology to Nuclear Power Plants (1977 : Vienna)
Publicado: (1978.)

Reglamento de equipos a presión.
Publicado: (2012)

Nuclear heat transport /
por: El-Wakil, M. M. 1921-
Publicado: (c1978.)

Obtención de funciones de dispersión en fantoma fuera del eje del haz /
por: Luna Dominguez, Mario Sergio.
Publicado: (2006.)

Flow-induced vibration, 1996 : excitation mechanisms in cross flow and nuclear fuel vibration, fretting-wear damage and piping vibration : presented at the 1996 ASME Pressure Vessels and Piping Conference, Montreal, Quebec, Canada, July 21-26, 1996 /
Publicado: (c1996.)

Análisis de fatiga en el RPR del reactor nuclear CAREM 25 /
por: Bustos, Raúl I.
Publicado: (2015.)

Automatización de las tareas de apertura y cierre de la tapa del reactor CAREM /
por: Nadal, Javier E.
Publicado: (2010.)

Estudio de los requerimientos de inspección en servicio de los componentes de retención de presión de CNA II /
por: Bourguigne, Gastón.
Publicado: (2010.)

Rol de la deformación plástica en el fenómeno de la propagación de una rajadura /
por: Vázquez, José A.
Publicado: (1972.)

Journal of pressure vessel technology.
Publicado: (c1974-)

Descripción de los sistemas Q, T, R y U de la central nuclear Atucha. /
por: Rauschert, Agustín Guillermo.
Publicado: (1996.)

Degradación de la transferencia térmica en el núcleo bajo hipótesis de accidente severo en Atucha I /
por: Azpitarte, Osvaldo E.
Publicado: (1993.)

Development of a D2O-reactor system for a nuclear power plant in the range of 350 to 600 MWe based on the reference plant Atucha I : feasibility study for Comisión Nacional de Energía Atómica /
Publicado: (1978.)

Desarrollo de un modelo de cálculo para dosimetría in vivo en haces de fotones conformados de alta energía /
por: Álvarez, Guillermo Daniel.
Publicado: (2004.)

Principles of radiation dosimetry /
por: Whyte, George Neilson.
Publicado: ([1959])

Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry, Strasbourg, France, 27-31 August 1990 /
por: ASTM-Euratom Symposium on Reactor Dosimetry (7th : 1990 : Strasbourg, France)
Publicado: (c1992.)

Riesgo y daño nuclear de las centrales nucleares /
por: Tocino Biscarolasaga, Isabel, 1949-
Publicado: (1975, c1969.)

Materials specifications /
Publicado: (1983.)

Proceedings of second International Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, Tokyo, Japan, April 15-17, 1986 /
por: International Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations (2nd : 1986 : Tokyo, Japan)
Publicado: ([1986])

The management of risk to society from potential accidents : the main report of the UKAEA Working Group on the Risks to Society from Potential Major Accidents : with an executive summary /
Publicado: (c1992.)

Use of probabilistic safety assessment for operational safety, PSA '91 : proceedings of an International Symposium on the Use of Probabilistic Safety Assessment for Operational Safety /
por: International Symposium on the Use of Probabilistic Safety Assessment for Operational Safety (1991 : Vienna, Austria)
Publicado: (1992.)

Simulación digital de la Central Nuclear Atucha II /
por: Santomé, Daniel H.
Publicado: (1987.)

Modelado y simulación del sistema de regulación de la turbina hidraulica de la Central Atucha I /
por: Copparoni, Gustavo Mario.
Publicado: (1992.)

Rol del óxido nítrico en los efectos radioinducidos en corteza cerebral en desarrollo. /
por: Robello, Elizabeth.
Publicado: (2001.)

Extended and updated selected papers from the 17th Water : held at Holiday Inn Crowne Plaza, Rockville, Maryland, October 23-25, 1989.
por: Water Reactor Safety Information Meeting (17th : 1989 : Rockville, Md.)
Publicado: (1992.)

The safety of nuclear power : strategy for the future : proceedings of an International Conference on the Safety of Nuclear Power--Strategy for the Future /
por: International Conference on the Safety of Nuclear Power--Strategy for the Future (1991 : Vienna, Austria)
Publicado: (1992.)

Quality assurance for nuclear power plants : proceedings of an International Symposium on Quality Assurance for Nuclear Power Plants /
por: International Symposium on Quality Assurance for Nuclear Power Plants (1981 : Paris, France)
Publicado: (1982.)

Methods for reducing occupational exposures during the decommissioning of nuclear facilities : report of a technical committee meeting on the methods for reducing occupational exposures during the decommissioning of nuclear facilities /
Publicado: (1987.)

Nuclear power performance and safety : proceedings of an International Conference on Nuclear Power Performance and Safety /
por: International Conference on Nuclear Power Performance and Safety (1987 : Vienna, Austria)
Publicado: (1988-)