ROBERTO FRAJNDLICH
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Publicação IPEN-doc 02250 Tese IPEN-doc 20544 Considerações sobre o descomissionamento do reator de pesquisa IEA-R1 e futuro de suas instalações após o seu desligamento2014 - FRAJNDLICH, ROBERTOO Reator Nuclear de Pesquisa IEA-R1 em operação desde 1957 no Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP) é um dos reatores mais antigos do mundo em operação. Em algum momento no futuro, a exemplo de outros reatores, será desligado definitivamente. Antes de chegar este momento a organização operadora precisa planejar o futuro de suas instalações e definir o destino que pretende dar aos equipamentos e materiais radioativos e não radioativos que se encontram no interior das instalações. Estas questões devem estar contidas no chamado \"Plano de Descomissionamento Preliminar da Instalação\" que é o tema deste trabalho. O trabalho apresenta inicialmente uma visão geral sobre este tema e relaciona os objetivos gerais e específicos para sua realização, descrevendo a seguir, as diretrizes que a organização operadora deve considerar para formulação de um plano de descomissionamento. A estrutura atual do setor nuclear brasileiro enfatizando principalmente as normas utilizadas no gerenciamento do rejeito radioativo é apresentada. Uma descrição dos principais equipamentos do reator IEA-R1 que constituem o seu inventário radioativo e não radioativo é apresentada. O trabalho enfatiza também a experiência adquirida pelo corpo técnico do reator com as reformas e modificações realizadas na instalação durante sua vida útil. Esta experiência pode ser de grande valia por ocasião do descomissionamento do reator no futuro. Um experimento usando o método de espectrometria gama de alta resolução e cálculo computacional através da teoria de Monte Carlo foi realizado com o objetivo de se obter uma estimativa do volume de rejeito radioativo gerado pelo desmantelamento das paredes de concreto da piscina do reator. O custo do descomissionamento em função da estratégia escolhida é determinado utilizando o código CERREX. Por fim, é realizada uma discussão sobre as diferentes estratégias consideradas. Na base destas discussões conclui-se que a estratégia mais vantajosa a ser adotada no caso deste reator é aquela que preserva o seu prédio e instalações anexas, tendo em vista o grande volume de rejeito radioativo e custos sensivelmente maiores que resultariam com o seu desmantelamento. É sugerida a preservação de parte das equipes de operação, manutenção, proteção radiológica e física da instalação e utilização do prédio do reator e anexos para divulgação da energia nuclear através de sua transformação em um museu, uma vez que este foi o primeiro reator nuclear construído no Brasil e, desde sua inauguração, tem sido utilizado como forma de divulgação da energia nuclear no país.Capítulo IPEN-doc 14654 Capítulo IPEN-doc 15611 Spent fuel management options for research reactors in Latin America2006 - ADELFANG, PABLO; MATTAR NETO, MIGUEL; TEIXEIRA e SILVA, ANTONIO; MAIORINO, JOSE R.; FRAJNDLICH, ROBERTO; MARTINELLI, JOSE R.; SOARES, ADALBERTO J.Resumo IPEN-doc 13628 Comissioning of the heat exchanger for the research nuclear reactor IEA-R12008 - CASTRO, ALFREDO J.A. de; CASSIANO, DOUGLAS A.; UMBEHAUN, PEDRO E.; CARVALHO, MARCOS R. de; FRAJNDLICH, ROBERTOThe Research Reactor IEA-R1 placed at IPEN/CNEN-SP is of the swimming pool type, light water moderated and with graphite reflectors, and was build and designed by Babcock & Wilcox Co. Start up operation was in September the 16th, 1957, being the first criticality in South Hemisphere. Although designed to operate at 5 MW Power, the IEA-R1 was updated in 2001 to 2 MW operation and suitable for use in basic and applied research as well as the production of medical radioisotopes, industry and natural sciences. Due to a recent demand increase on radioisotopes in Brazil for medical diagnoses and therapies applications, IPEN in cooperation with CNEN updated the IEA-R1 potency to 5 MW and to work at continuous operation regime. Studies on the Ageing Management for the Research Reactor IEA-R1 were conducted according to IAEA procedures described in the technical report 338 (IAEA, 2001) and technical document 792 (IAEA, 1995). As result of these studies critical components within the Ageing Management Program were identified. Also recommendations on the implementation of a test schedule and a procedure to organize data and documents were made. The main result was the need to monitoring both heat exchangers, the two primary pumps and the data acquisition system. Along the monitoring process, difficulties were observed to operate the Reactor at 5 MW mainly due to the ageing of the TCA heat exchanger, Babcox&Wilcox, and vibration problems at high flow rates on TCB heat exchanger, by CBC. From 2005, it was chosen to work with 3,5 MW and to provide a new heat exchanger with 5 MW capacity , fabricated by IESA , to substitute the TCA heat exchanger. This work presents results on the commissioning of the new heat exchanger and compares to the values calculated on the Project. The results show that the IEA-R1 Reactor can be operated safety and continuously at the Power of 5 MW with the new heat exchanger.Artigo IPEN-doc 05888 Mudancas do reator IEA-R1 no regime de operacao de 48 horas continuas1995 - MOREIRA, J.M.L.; FRAJNDLICH, R.Artigo IPEN-doc 14355 The management system evolution of research nuclear reactor IEA-R12009 - SALVETTI, T.C.; PAIVA, R.P.; FRAJNDLICH, R.; LONGO, G.C.The IEA-R1 is the first research nuclear reactor in Brazil and since its inauguration in 1957, has been regularly used mainly for R&D, teaching and production of some radioisotopes for medical and other purpose. Until 1999 the IEA-R1 reactor adopted a Quality Assurance Program based on the Brazilian regulatory body standard (Brazilian Nuclear Energy Commission - CNEN) CNEN NN 1.16 and the IAEA Guide SS 50 CQ to control quality and safety requirements, quality procedures and records. In 2001 the Research Reactor Center (CRPq) has began to implement a Quality Management System (QMS) focused on “Operation and Maintenance of the IEA-R1 Research Reactor and Irradiation Services". In 2002 this facility obtained its first NBR ISO 9001:2000 certification on this scope. The present work relates the stages involving the implementation of QMS of IEA-R1 reactor since it started operation until now, reporting the mainly difficulties and results obtained.Artigo IPEN-doc 15308 IEA-R1 research reactor: operational life extension and considerations regarding future decommissioning2009 - FRAJNDLICH, ROBERTOArtigo IPEN-doc 13482 Comissioning of the new heat exchanger for the research nuclear reractor IEA-R12008 - CASTRO, ALFREDO J.A. de; CASSIANO, DOUGLAS A.; UMBEHAUN, PEDRO E.; CARVALHO, MARCOS R. de; FRAJNDLICH, ROBERTOThe Research Reactor IEA-R1 placed at IPEN/CNEN-SP is of the swimming pool type, light water moderated and with graphite reflectors, and was build and designed by Babcock&Wilcox Co. Start up operation was in September the 16th, 1957, being the first criticality for South Hemisphere. Although designed to operate at 5 MW, the IEA-R1 was operated until 2001 with 2 MW and was suitable for use in basic and applied research as well as the production of medical radioisotopes, industry and natural sciences applications. Due to a recent demand increase on radioisotopes in Brazil for medical diagnoses and therapies applications, IPEN /CNEN updated the IEA-R1 power to 5 MW and to work at continuous operation regime. Studies on the Ageing Management for the Research Reactor IEA-R1 were conducted according to IAEA procedures. As result of these studies critical components within the Ageing Management Program were identified. Also were made recommendations on the implementation of test scheduling and standardization procedures to organize data and documents. One of the main results was the need of monitoring the two heat exchangers, the two primary circuit pumps and the data acquisition system. During monitoring procedures, issues were observed on the IEA-R1 operation at 5 MW mainly due to the ageing of the Babcox & Wilcox TCA heat exchanger, and excessive vibrations at high flow rates on CBC’s TCB heat exchanger. So, from 2005 on, it was decided to work with 3,5 MW and provide a new IESA heat exchanger with 5 MW capacity, to substitute the TCA heat exchanger. This work presents results on the commissioning of the new heat exchanger and compares against the values calculated in the IESA project. The results show that the IEA-R1 Reactor can be operated more safety and continuously at 5 MW with the new IESA heat exchanger .Artigo IPEN-doc 11993 Experience of IPEN-CNEN/SP in the executation of the first phase of the safety culture enhancement programme at IEA-R1 research reactor2007 - VIEIRA NETO, ANTONIO S.; MARRA NETO, ADOLFO; OLIVEIRA, PATRICIA da S.P. de; SAXENA, RAJENDRA N.; CARVALHO, RICARDO N. de; FRAJNDLICH, ROBERTO; PAIVA, ROSEMEIRE P.
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