Hostname: page-component-78c5997874-dh8gc Total loading time: 0 Render date: 2024-11-02T23:21:41.787Z Has data issue: false hasContentIssue false
  • English
  • Français

The Spanish Radioactive Waste Management and the associated research ensuring its development from sound technical and scientific basis

Published online by Cambridge University Press:  23 March 2012

Pablo Zuloaga  and
Julio Astudillo
Pablo Zuloaga
Affiliation:
ENRESA, Emilio Vargas 7, Madrid 28043, Spain.
Julio Astudillo
Affiliation:
ENRESA, Emilio Vargas 7, Madrid 28043, Spain.
Get access

Abstract

Spanish Radioactive Waste Management policy is established by the Government and implemented by ENRESA. The General Plan (GRWP) covers the analysis of the actual and foreseen inventories of spent fuel and all categories of radioactive waste, their present situation, the management strategy and actions identified, as well as funding and financial provisions. Very Low (VLLW) and Low and Intermediate Level Waste (LILW) are disposed of at El Cabril facility, which has two separate disposal areas: one intended for VLLW, based on clay and polyethylene and started up in 2006; and one for LILW conditioned in retrievable concrete containers, commissioned in 1992. Spent fuel (SF) is being stored in pools and in two dry storage installations. The priority is the development of the SF and HLW centralized storage facility. In 2009, the Government launched a call for candidate municipalities, in a public, participative process. In September 2010 a report was sent to the Cabinet, proposing eight volunteer communities, four of them deemed preferred. In the 90’s a deep geological repository (DGR) site identification program was carried out. DGR basic designs and associated performance assessments were developed in three rock types. ENRESA has set a research program that includes research projects in order to strengthen the link between management and scientific basis and improve the performance assessment, directed to the behavior of barriers, fuel or waste forms in different storage and final disposal conditions, and characterization techniques. There is also a participation in connected fields or supporting decision-making, such as advanced separation and transmutation.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1475: Symposium NW – Scientific Basis for Nuclear Waste Management XXXV , 2012 , imrc11-1475-nw35-il03
Copyright
Copyright © Materials Research Society 2012

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Ministerio de Industria, Turismo y Comercio. Spain. 6th General Radioactive Waste Plan. June 2006 Google Scholar
2. Consejo de Seguridad Nuclear. Resolución por la que se aprueba la apreciación favorablemente del diseño genérico propuesto por ENRESA del Diseño genérico del Almacén Temporal Centralizado (ATC) de Combustible Gastado y residuos de Alta Actividad. July 2006 Google Scholar
3. Ministerio de Industria, Turismo y Comercio. Resolución del Secretario de Estado de Energía de 23 de diciembre de 2009 sobre convocatoria de municipios candidatos para albergar el almacén centralizado de combustible gastado. BOE. 29 December, 2009.Google Scholar
4. Zuloaga, P. Spent Nuclear Fuel Management in Spain. IAEA. International Conference on Spent Fuel from Nuclear Power Reactors. 31 May - 4 June 2010 Vienna, Austria Google Scholar
5. Andrade, C, Castellote, M, Martínez, I, Zuloaga, P, Navarro, M, Ordóñez, M. 2005. Concrete behaviour in engineered barriers for low and medium level radioactive waste repository: example of El Cabril, Cordoba, Spain. 6th International Congress Global Construction: Ultimate Concrete Opportunities. Dundalk, UK, June 2005 Google Scholar
6. USNRC. Spent Fuel Project Office. Interim Staff Guidance - 11, Revision 3. Cladding considerations for the transportation and storage of spent fuel. 2003 Google Scholar
7. Johnson, AB Jr, Gilbert, ER, Technical basis for storage of Zircaloy-clad spent fuel in inert gases, PNL-4835, 1984 Google Scholar
8. Zuloaga, P, Andrade, C, Rodríguez, J, García, M, Palacio, J. Electrochemical techniques to detect corrosion in concrete structures in nuclear installations. OECD-NEA Workshop on the Instrumentation and Monitoring of Concrete Structures. Brussels, 22–23 March 2000 Google Scholar
9. Andrade, C, Rodriguez, J, Jimenez, F, Palacio, J and Zuloaga, P, Embedded sensors for concrete structures instrumentation. OECD-NEA Workshop on Instrumentation and Monitoring of Concrete Structures Brussels (Belgium). 2000 Google Scholar
10. Andrade, C, Martínez, I, Castellote, M and Zuloaga, P. Some principles of service life calculation of reinforcements and in situ corrosion monitoring by sensors in the radioactive waste containers of El Cabril disposal (Spain) Journal of Nuclear Materials 358 (2006) 82–95 10.1016/j.jnucmat.2006.06.015Google Scholar
11. Astudillo, J. 6th R&D Plan. Estratos. October 2006 Google Scholar
12. Zuloaga, P, Andrade, C, Castellote, M. Ageing Management Program. Ageing management program for the Spanish low and intermediate level waste disposal and spent fuel and high-level waste centralised storage facilities 01003 12 April 2011. DOI: 10.1051/epjconf/20111201003 10.1051/epjconf/20111201003Google Scholar