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Master's Dissertation
DOI
10.11606/D.85.2018.tde-08052018-112533
Document
Author
Full name
Dayane Faria Silva
E-mail
Institute/School/College
Knowledge Area
Date of Defense
Published
São Paulo, 2017
Supervisor
Committee
Sabundjian, Gaianê (President)
Kuramoto, Renato Yoichi Ribeiro
Silva, Antonio Teixeira e
Title in Portuguese
Análise do comportamento da contenção do reator Angra 2 durante um acidente de base de projeto
Keywords in Portuguese
Angra 2
COCOSYS
contenção
LBLOCA
RELAP5
Abstract in Portuguese
Este trabalho visa verificar a integridade da contenção do reator de Angra 2, com uma abordagem mais realista, da possibilidade de conter todos os radionuclídeos gerados durante Acidentes de Perda de Refrigerante Primário por Grande Ruptura (Large Break Loss of Coolant Accident - LBLOCA). Além disso, essas informações são utilizadas para o cálculo mais realista do Pico de Temperatura do Encamisamento (PTE) da vareta mais realista do núcleo deste reator durante esse acidente. Os resultados desse estudo possibilitarão verificar a integridade da Planta após a ocorrência de acidentes considerados base de projeto. Alguns dos programas utilizados para analisar a contenção de uma usina nuclear são o RELAP5 e o COCOSYS. Esses códigos computacionais são ferramentas de análise que preveem as condições termohidráulicas dentro de um prédio de contenção de um reator refrigerado à água leve. A contenção da planta tipo Pressurized Water Reactor (PWR) é um edifício de concreto revestido internamente por metal e tem limites de pressão que devem ser respeitados durante a ocorrência de um acidente. Os dados de entradas necessários para esta simulação são: adição de massa e energia geradas do estudo de um acidente do tipo LBLOCA com o código RELAP5 da planta em questão. Os resultados da análise do comportamento da contenção da planta nuclear Angra 2 durante os acidentes base de projetos estudados rupturas do tipo guilhotina do circuito primário nas pernas fria e quente foram satisfatórios quando comparados com os apresentados no Relatório de Análise de Segurança (RFAS/A2) da planta e as distribuições de pressão ficaram bem abaixo do valor de pressão de projeto da contenção (6,3bar).
Title in English
Analysis of the behavior of the Angra 2 reactor containment during a design basis accident
Keywords in English
Angra 2
COCOSYS
containment
LBLOCA
RELAP5
Abstract in English
This work aims to verify the integrity of Angra 2 reactor containment by using a more realistic approach for the possibility of containing all radionuclides generated during a Large Break Loss of Coolant Accident (LBLOCA). In addition, this information is used for a more realistic calculation of the Peak Cladding Temperature (PCT) of the hottest area in the reactor during this accident. This study will contribute to the safety of the population from the surrounding areas after the occurrence of a design basis accident. Some of the programs used to analyze the containment of a nuclear plant are RELAP5 and COCOSYS. These computers codes are tools for analysis used for predicting the physical conditions and distributions of radionuclides inside a containment building following the release of material from the primary system in a light-water reactor accident. The containment of the type PWR plant is a concrete building coated internally with metal and has pressure limits to be respected during the occurrence of an accident. The simulation should be performed to ensure that the radionuclides originating from accidents in the plant are not released into the environment. The input data required for this simulation are: mass addition and energy generated from the simulation of an accident of the type Loss of Coolant Accident (LOCA) using RELAP5 code. The results of the analysis of the containment behavior of the Angra 2 nuclear plant during the design basis accidents studied - guillotine-type ruptures of the primary circuit in the cold and hot legs - were satisfactory when compared to those presented in the Final Safety Analysis Report (FSAR) of the plant; moreover, the pressure distributions were below the contention design pressure value (6.3bar).
 
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2017SilvaAnalise.pdf (8.70 Mbytes)
Publishing Date
2018-06-21
 
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