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| Author(s): |
Douglas Borges Domingos
Total Authors: 1
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| Document type: | Master's Dissertation |
| Press: | São Paulo. |
| Institution: | Universidade de São Paulo (USP). Instituto de Pesquisas Energéticas e Nucleares (IPEN/BT) |
| Defense date: | 2010-04-15 |
| Examining board members: |
Antonio Teixeira e Silva;
João Manoel Losada Moreira;
Luis Antonio Albiac Terremoto
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| Advisor: | Antonio Teixeira e Silva |
| Abstract | |
Neutronic, thermal-hydraulics and accident analysis calculations were developed to estimate the safety of a Miniplate Irradiation Device (MID) to be placed in the IEA-R1 reactor core. The irradiation device is used to receive miniplates of U3O8-Al and U3Si2- Al dispersion fuels, LEU type (19.75 % 235U) with uranim densities of, respectively, 3.2 gU/cm3 and 4.8 gU/cm3. The fuel miniplates will be irradiated to nominal 235U burnup levels of 50% and 80%, in order to qualify the above high-density dispersion fuels to be used in the Brazilian Multipurpose Reactor (RMB), now in the conception phase. For the neutronic calculation, the computer codes CITATION and 2DB were utilized. The computer code FLOW was used to calculate the coolant ow rate in the irradiation device, allowing the determination of the fuel miniplate temperatures with the computer model MTRCR-IEA-R1. A postulated Loss of Coolant Accident (LOCA) was analyzed with the computer codes LOSS and TEMPLOCA, allowing the calculation of the fuel miniplate temperatures after the reactor pool draining. The calculations showed that the irradiation should occur without adverse consequences in the IEA-R1 reactor. (AU) | |