Chang Alcover, Ariel (2019) Diseño de blindajes y protección radiológica de un reactor de fusión tipo MIT ARC. / Desing of shielding and radiological protection of a fusion reactor type MIT ARC. Integration Project in Nuclear Engineering, Universidad Nacional de Cuyo, Instituto Balseiro.
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Abstract in Spanish
El ARC (asequible, robusto, compacto) es un diseño conceptual de una planta piloto de fusión de 525MW de potencia de fusión. El ARC propone varias soluciones novedosas, como el uso de superconductores de alta temperatura, espiras desmontables y un blanket liquido reproductor de tritio de FLiBe. Se presenta el diseño conceptual del blindaje de las espiras toroidales, así como el blindaje biológico. Se analizan la activación y el calor de decaimiento de distintos componentes luego de 10 años a plena potencia. Para esto se desarrollo un modelo simplificado del reactor y se lo analizo con el código computacional MCNP. Se analiza la importancia del enriquecimiento de Li-6 en el blanket de FLibe y de las paredes de tungsteno y berilio en el valor de la tasa de generación de tritio. Se identifican los componentes principales del circuito primario de refrigeración considerando un ciclo rankine de dos lazos independientes. Empleando el código de calculo de blindajes MicroShield se proponen los blindajes de las componentes del primario.
Abstract in English
The ARC (affordable, robust, compact) is a pilot plant conceptual design with 525MW of fusion power. ARC has high temperature superconducting toroidal field coils, which have joints to enable disassemble and a liquid blanket tritium breeding consisting of FLiBe. The conceptual design of the shielding of the toroidal eld coils is presented, and the biological shielding. The activation and decay heat of different components are analyzed after 10 years at full power. A simplied model of the reactor is developed with the radiation transport code MCNP. The importance of the enrichment of Li-6 in the blanket of FLiBe and the walls of tungsten and berylium in the value of tritium breeding ratio is analyzed. The main components of the primary cooling circuit are identified considering a rankine cycle of two independent loops. The MicroShields calculation code is employed to propose the shielding of the components of the primary.
| Item Type: | Thesis (Integration Project in Nuclear Engineering) |
|---|---|
| Keywords: | Fusion reactors; Reactores de fusión; Shields; Blindajes; Radiological protection; Protección radiológica |
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| Subjects: | Nuclear engineering > Fusión nuclear |
| Divisions: | INVAP |
| ID Code: | 830 |
| Deposited By: | Tamara Cárcamo |
| Deposited On: | 10 Mar 2021 10:08 |
| Last Modified: | 10 Mar 2021 10:08 |
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