[en] The RRFM Conference is organized by the European Nuclear Society (ENS) with co-operation of the IAEA. It includes detailed scientific and technical reports reports on the following main topics: Fuel development, qualification, fabrication and licensing; Spent fuel management, back-end options and transportation; Reactor operation, fuel safety and core conversion; Innovative methods in research reactor analysis; Global Treat Reduction Initiative

[en] The paper presents an overview of the IAEA role in the management of research reactors fuel.Examples of Research Reactor Fuel Conversion Projects are given. The IAEA activities to support for the repatriation, management and disposal of fresh and (or) spent fuel are presented. The IAEA mechanisms to facilitate RERTR/RRRFR and GTR programs and to ensure the HEU/LEU conversion and return of the unneeded fresh fuel and stored spent fuel to the country of origin and to ensure a high level of safety are also discussed

[en] The mission of the Section, main activities and future plans are presented. The enhancing of the safety of research reactors and fuel cycle facilities is based on the IAEA documents - Code of Conduct on the Safety Research Reactors and Safety Standards and associated guidance publications on RRs and FCFc. The activities of the section include: INSSARR missions; Coordinated Research Programs; maintenance of the Incident Reporting System for Research Reactors (IRSRR) and Fuel Cycle Facilities (FINAS) as well as education and training. The Technical Documents prepared by the Section and TC activities are also presented

[en] The RERTR program supports the minimization and, to the extent possible, elimination of the use of HEU in civil nuclear applications by working to convert research and test reactors and radioisotope production processes to the use of LEU fuel and targets throughout the world. (author)

[en] During the past 50 years worldwide, 70 TRIGA reactors have been commissioned, including those constructed by General Atomics and those converted into TRIGA reactors. This is actually the best selling low-to-medium power reactor based on a simple and inherently safe concept. Therefore these reactor types were mainly installed at universities and hospitals. This paper presents a review of TRIGA performances and utilizations worldwide as replied to the sent questionnaire and shows the broad range of research activities. (author)

[en] The Petten HFR will be fully converted to LEU fuel by 06 May 2006. The used fuel is U₃Si₂ at a density of 4.8 g·cm^-3. Cadmium wires are applied as burnable poison. Two sets of reactor physics codes are used to support the conversion process. Thanks to extensive and ongoing validation of the codes and models a very good agreement between measurement and calculation is achieved. As a result of the conversion the thermal flux drops by about 15%. Switching to cadmium wires as burnable poison resulted in a better reactivity performance of the HFR core. (author)

[en] The Rossendorf Research Reactor (RFR) had been in operation from 1957 to 1991. In 1991 the final shut down of the reactor was decided. The Nuclear Engineering and Analytics Rossendorf Inc. (VKTA) was charged with the decommissioning of the RFR. One of the main decommissioning objectives was the management of the irradiated fuel elements. The key elements of the fuel element management were the use of a dry loading method based on the storage and transport cask CASTOR MTR 2 and the use of a buffer storage at the VKTA site for the loaded casks until the transfer into the interim storage facility at Ahaus (BZA) was possible. All process steps could be completed successfully in the middle of 2005. (author)

[en] Corrosion and mechanical damage may appear on the aluminum based fuel surface during long term wet interim storage. Experience has shown that video imaging can provide information about the general structural conditions of the fuel and/or the nature or type of damage suffered. Therefore, a fuel visual inspection program by means of underwater video equipment should be set in storage facilities. This work presents a proposal of damage degree classification for MTR type spent fuel by means of the evaluation of photographic images, and the basic technical features of a visual inspection program applicable to wet interim storage, with the purpose of establishing common criteria for storage facility operators. (author)

[en] The collaboration of global partners AREVA and GTRI is presented in this paper for achieving of the nonproliferation and nuclear security objectives. It is through these efforts that the risk of diversion or theft of nuclear weapons usable material has been decreased by reducing the proliferation or terrorist attractiveness of the material, redirecting the material towards peaceful uses

[en] In the frame of the collaboration agreement recently signed between CEA, TUM and CERCA aiming to evaluate the behaviour of monolithic UMo full size prototype plates in the OSIRIS reactor, this paper states the manufacturing development program which is being carried out. Technical aspects as UMo ingot manufacturing, thin UMo foils elaboration and plates production are presented. (author)