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[en] We report on the repatriation of spent nuclear fuel of the Siemens-Argonaut zero power research reactor Graz (WAGL). This reactor had two cores, one LEU core consisting of 234 aluminum coated fuel plates and one HEU core consisting of 125 aluminum coated fuel plates. The maximum burn-up was 10-4% according to the FIFA definition (Fission per Initial Fissile Atom). This low burn-up resulted in simplified loading operations because of the very low radiation level. A detailed description of the reactor site will be given in its relevance to the loading operations. We will discuss further the planning phase, problems in selecting a feasible transport route, national regulations and we will also give details of the timeline. (author)
Source
International Atomic Energy Agency, Nuclear Fuels Cycle and Materials Section, Vienna (Austria); 349 p; ISBN 978-92-0-105508-8; 
; ISSN 1011-4289; ; Aug 2008; p. 67-76; Technical meeting on return of research reactor spent fuel to the country of origin: Requirements for technical and administrative preparations and national experiences; Vienna (Austria); 28-31 Aug 2006; Also available on-line: http://www-pub.iaea.org/MTCD/publications/PDF/TE_1593_Web.pdf; For availability on CD-ROM, please contact IAEA, Sales and Promotion Unit: E-mail: sales.publications@iaea.org; Web site: http://www-pub.iaea.org/MTCD/publications/publications.asp; 5 refs, 6 figs
; ISSN 1011-4289; ; Aug 2008; p. 67-76; Technical meeting on return of research reactor spent fuel to the country of origin: Requirements for technical and administrative preparations and national experiences; Vienna (Austria); 28-31 Aug 2006; Also available on-line: http://www-pub.iaea.org/MTCD/publications/PDF/TE_1593_Web.pdf; For availability on CD-ROM, please contact IAEA, Sales and Promotion Unit: E-mail: sales.publications@iaea.org; Web site: http://www-pub.iaea.org/MTCD/publications/publications.asp; 5 refs, 6 figs