Durability of a reinforced concrete designed for the construction of an intermediate-level radioactive waste disposal fa
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Durability of a reinforced concrete designed for the construction of an intermediate-level radioactive waste disposal facility G.S. Duffó (1, 2, 3), E.A. Arva (3), F.M. Schulz (1) and D.R. Vazquez(3) (1)
Consejo Nacional de Investigaciones Científicas y Técnicas, Argentina Universidad Nacional de Gral. San Martín, Argentina (3) Comisión Nacional de Energía Atómica, Departamento de Materiales, Av. Gral. Paz 1499 (1650), San Martín, Buenos Aires, Argentina. E-mail: [email protected] (2)
ABSTRACT The National Atomic Energy Commission of the Argentine Republic is developing a nuclear waste disposal management programme that contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive wastes. The repository is based on the use of multiple, independent and redundant barriers. The major components are made in reinforced concrete so, the durability of these structures is an important aspect for the facility integrity. This work presents an investigation performed on a reinforced concrete specifically designed for this purpose, to predict the service life of the intermediate level radioactive waste disposal facility from data obtained with several techniques. Results obtained with corrosion sensors embedded in a concrete prototype are also included. The information obtained will be used for the final design of the facility in order to guarantee a service life more or equal than the foreseen durability for this type of facilities. INTRODUCTION Since 1950, the National Atomic Energy Commission (CNEA) of the Argentine Republic works on the development of nuclear energy applications for pacific purposes. The tasks include the operation of important facilities in charge of the production of radioisotopes for medical and industrial applications and the performance of tasks in connection with the nuclear fuel cycle, manufacturing of fuel elements and the operation of two nuclear power plants. As a result of such activities performed in the nuclear field by CNEA and other private and public entities, various types of radioactive waste are being produced. The CNEA is the implementing authority to perform all activities related to the radioactive waste management and sets up the Radioactive Waste Management National Program (PNGRR) [1]. In order to achieve its objectives the PNGRR is in charge of the adoption of the most appropriate technological solution for the management of such wastes and the scientific-technological support. At the end of the 1990s, the CNEA started an extended research programme which final purpose was to design a facility for the disposal of Intermediate Level Radioactive Waste (ILRW) and to study the long-term behaviour of the materials used for its construction. ILRW is originated from operation and maintenance activities of the two Argentine Nuclear Power Plants (Atucha I and Embalse), and consist mainly of mechanical filters from the primary circuit of the reactor and by spent ionic exchange resin beds. In this context, a near-surface monolithic repositor
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