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The Reduced Enrichment for Research and Test Reactors (RERTR) Program was initiated by the United States Department of Energy in 1978 with the mission of developing the technologies necessary to convert research and test reactors from the use of fuels containing highly-enriched uranium (HEU) to the use of fuels containing low-enriched uranium (LEU). The overall objective of the program was to reduce international commerce in weapons grade uranium.[1] In 1978, a similar program was started in the Soviet Union with the goal of reducing the enrichment level of research reactor fuels. During the 1980s, the Soviet Union also changed its policies regarding the export of fuel for Soviet-built research reactors abroad, thenceforth supplying them with 36% HEU in lieu of 90% HEU. However, activities to reduce enrichment levels were hampered in the late 1980s by the economic and political problems within Russia. At the same time, with the collapse of the Soviet Union, contacts with foreign experts and the exchange of information on these issues increased. Since 1993 Russian scientists have been participating in International RERTR meetings.[2] In September 1994, representatives of the US Department of Energy and Russian Ministry of Atomic Energy signed a protocol of intent to reduce fuel enrichment in civilian research and test reactors. These efforts go in two directions: 1) development of higher-density 19.75% enriched uranium fuels and 2) demonstration of feasibility of and conversion to LEU fuel of specific reactors. The main Russian organizations involved in this effort are the Scientific Research and Design Institute of Energy Technologies (NIKIET), the Institute for Inorganic Materials (VNIINM), the Novosibirsk Chemical Concentrate Plant (NZKhK), and the Kurchatov Institute. Scientists from these organizations conduct studies to determine the technical and economic feasibility of converting Russian-supplied research and test reactors to use LEU fuels. An important part of this effort is the development of computer models to interpret and predict the behavior of various fuels that might be irradiated in Russian-designed reactors. These models are being developed through a joint effort between Argonne National Laboratory and VNIINM scientists.[3] The 2000 RERTR program
status report
presented by the Argonne National Laboratory at the October 2000 International RERTR Meeting in Las
Vegas noted progress on the irradiation
testing of LEU UO2 dispersion fuel and on LEU conversion
feasibility studies in the Russian RERTR
program. Studies have been conducted to investigate the feasibility of
converting the following reactors to the use of LEU U-Mo fuels: the
VVR-M reactor at the
St. Petersburg Nuclear
Physics Institute, the
IR-8 reactor at the
Kurchatov Institute, the VVR-SM research reactor in Uzbekistan, and the MARIA
reactor in Swierk, Poland. [4]
Page last updated 2 February 2005 Comments or questions? Contact Contact Cristina Chuen at MIIS CNS: Cristina.ChuenATmiis.edu
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