Methodology for Management and Physicochemical Control of the Cooling Water of the IPR-R1 Triga Nuclear Research Reactor
DOI:
https://doi.org/10.15392/2319-0612.2022.1857Keywords:
IPR-R1 Triga research reactor, cooling water, physicochemical control.Abstract
The IPR-R1 Triga research reactor, located at CDTN (Nuclear Technology Development Center) in Brazil, is one of the oldest reactors in operation worldwide. The Brazilian Nuclear Energy Commission (Cnen) has granted a Permit for Permanent Operation license for the CDTN Triga reactor. This authorization includes some conditions to be settled within a period of up to two years, that is, until the end of 2019, which has not yet been carried out and is currently being prepared by CDTN. For this purpose, Project 0006.23 – Maintenance of Licensing of the IPR-R1 Triga Reactor was created in CDTN's Multiannual Program. In this project is included the Subproject: 6.23.3 – Preparation of the system to manage the aging of the IPR-R1 Triga reactor. Inserted in this context, the main objective of this paper is the proposal of good practices to be adopted in the future by CDTN, related to the Projects of Licensing and Aging of Triga reactor, for the management and physicochemical control of its cooling water, considering its electrical conductivity and pH, following IAEA recommendations. So, the present work is relevant, as it addresses a proposal for monitoring and controlling pH and electrical conductivity of the cooling water of Triga reactor. As a result of this proposal, the useful life of Triga reactor may be extended and there will be greater reliability and safety in its operation.
- Views: 162
- PDF Downloads: 107
Downloads
References
MESQUITA, A. Z.; REZENDE, H. C.; TAMBOURGI, E. B. Calibração da Potência do Reator Nuclear de Pesquisa TRIGA IPR-R1, durante os Testes de Aumento de Potência de 100 kW para 250 kW. Res and Dev Braz J, v. 4, no. 2, 2002.
RODRIGUES, R. R.; MESQUITA, A. Z.; PALMA, D. A. P. Designing a system to detect leak-ing in fuel elements in Brazilian Triga research reactor. Int J Nuc Energ, Sci and Tec (Print), v. 12, p. 239, 2018. DOI: https://doi.org/10.1504/IJNEST.2018.095691
IAEA - International Atomic Energy Agency. Ageing Management for Research Reactors. Safety Standards Series, No SSG-10, PUB 1447, Specific Safety Guide, Vienna, 2010.
IAEA - International Atomic Energy Agency. Good practices for water quality management in research reactors and spent fuel storage facilities. IAEA Nuclear Energy Series, No. NP-T-5.2, STI/PUB/1492, Vienna, 2011.
IAEA - International Atomic Energy Agency. Operational Limits and Conditions and Oper-ating Procedures for Research Reactors. IAEA Safety Standards Series No. NS-G-4.4, STI/PUB/1333, Vienna, 2008.
IAEA - International Atomic Energy Agency. Instrumentation and Control Systems and Software Important to Safety for Research Reactors. IAEA Safety Standards Series No. SSG-37, STI/PUB/1692, Vienna, 2015.
ANSI/ANS – American National Standard/American Nuclear Society. The Development of Technical Specifications for Research Reactors. ANSI/ANS-15.1, Illinois, 2007.
MESQUITA, A. Z. Atualização e Recuperação da Instrumentação do Reator Nuclear Triga IPR-R1. Projeto de Pesquisa Fapemig, Proc: TEC-PPM-00032-08, Relatório Final, Programa Pesquisador Mineiro PPM II, 2008.
SIGNET, G. F. 8850-2 conductivity/resistivity transmitter manual. USA George Fischer Signet, 3-8850.090-2, Rev. H 8/06, 2001.
PROVITEC. Manual de instalação e calibração do PH 1000. São Paulo, 2002.
ALMEIDA, V. F. Investigação Teórico Experimental dos Parâmetros Físico-Químicos do Re-frigerante dos Reatores Nucleares Refrigerados a Água Leve. Dissertação, Mestrado em Ciência e Tecnologia das Radiações, Materiais e Minerais, CDTN, 2020.
NATIONAL INSTRUMENTS Co. Measurement and Automation - Graphical Program-ming for Instrumentation. Austin, 2007.
HOLLER, F.J.; SKOOG, D.A.; CROUCH, S.R. Princípios de Análise Instrumental. 6 th ed., Porto Alegre: Bookman, 2009.
RODRIGUES, R. R. Relatório de Análises de Água de Refrigeração do Reator Período de Junho de 2016 a Maio de 2017. Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), NI-Setre-001/17, Belo Horizonte, 2017.
RODRIGUES, R. R. Sistema para Inspeção de Elementos Combustíveis de Reatores Nucleares de Pesquisa pelo Método de “Sipping”. Tese. Doutorado em Ciência e Tecnologia das Radi-ações, Minerais e Materiais. Centro de Desenvolvimento da Tecnologia Nuclear (CDTN). Orientador: MESQUITA, A.Z. Belo Horizonte, 2018.
Published
How to Cite
Issue
Section
License
Copyright (c) 2022 Brazilian Journal of Radiation Sciences
This work is licensed under a Creative Commons Attribution 4.0 International License.
Licensing: The BJRS articles are licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. The images or other third party material in this article are included in the article’s Creative Commons license, unless indicated otherwise in a credit line to the material. If material is not included in the article’s Creative Commons license and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0/
