Caccia, Federico (2014) Diseño conceptual de un reactor rápido. / Fast reactor conceptual design. Integration Project in Nuclear Engineering, Universidad Nacional de Cuyo, Instituto Balseiro.
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Abstract in Spanish
En el presente trabajo se analizan distintos aspectos en el diseño conceptual de un reactor rápido. El estudio está enfocado hacia reactores reproductores y comienza con la investigación de distintas alternativas. La herramienta utilizada a lo largo del trabajo es la línea CONDOR-CITVAP que no está validada para el cálculo de reactores rápidos y por ello se realiza un benchmark. El trabajo continúa con el análisis de distintos parámetros de diseño a nivel de elemento combustible y de núcleo. Hacia el final del trabajo se reúne el conocimiento ganado en el diseño del núcleo de un reactor rápido.
Abstract in English
This work discusses various aspects in the conceptual design of a fast reactor. The study is focused on breeder reactors and begins researching dierent choices. The calculation tool used throughout the work is the line CONDOR-CITVAP which is not validated in fast reactor calculations and for this reason a benchmark is done. The work continues with analysis of dierent design parameters in fuel-assemblies and core level. At the end of the work, knowledge gained in fast reactor core design is gathered.
Item Type: | Thesis (Integration Project in Nuclear Engineering) |
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Additional Information: | Materia específica: Neutrónica |
Keywords: | Void coefficient; Coeficiente huecos; Doppler coefficient; Coeficiente doppler; Helium; Helio; Burnup; Grado de quemado; [CITVAP; CONDOR; MOX; Plutonium vector; Vector de plutonio] |
References: | [1] Alan E.Waltar, P. V., Donald R.Todd. Fast Spectrum Reactors. 2012. 2, 3, 8, 19, 35, 79, 111 [2] Technology Roadmap Update for Generation IV Nuclear Energy Systems. 2014. 9 [3] A technology Roadmap for Generation IV Nuclear Energy Systems. 2001. 11, 12, 13 [4] Status Report on the Small Secure Transportable Autonomous Reactor (SSTAR)/Lead-Cooled Fast Reactor (LFR) and Supporting Research and Developmen. 2006. 12 [5] Alamberti, A. ELSY The European Lead Fast Reactor. 2009. 12 [6] Villarino, E. CONDOR calculation package. 2002. 27 [7] IAEA-TECDOC-1623. BN-600 Hibrid Core Benchmark Analyses. 2010. 28, 30, 41, 117 [8] Authority, N. D. NDA Plutonium Options. 2008. 49 [9] John B Nims, E. M. P. Minimizing the positive sodium void coecient in liquid metal-cooled fast reactor systems. 1968. 55 [10] Furlano, L. Validacion de codigo de calculo CONDOR para redes de plantas de potencia en funcion de quemado. Proyecto Fin de Carrera, 2013. 59 [11] IAEA-TECDOC-1531. Fast Reactor Database 2006 Update. 2006. 66 [12] SUN, K. Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics. Tesis Doctoral, 2012. 68 [13] Devictor, N. Pre-conceptual design study of ASTRID core. 2012. 87 |
Subjects: | Nuclear engineering > Reactor engineering |
Divisions: | INVAP |
ID Code: | 468 |
Deposited By: | Marisa G. Velazco Aldao |
Deposited On: | 14 Oct 2014 11:51 |
Last Modified: | 15 Oct 2014 10:34 |
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