The Institute of Physics and Power Engineering (IPPE) at Obninsk is home to sev-eral fast research reactors. The BR-1 is a critical assembly commissioned in 1955, which was used to experimentally confirm plutonium breeding. It now serves as a testified neutron source for calibration of detectors, specimens, and instrumentation. An experimental mercury-cooled BR-2 began operating in 1956 but was closed down after a year. IPPE also has a fast critical facility, BFS-2, used for studying physical parameters of fast reactors including full-scale core simulation. The BR-5 has been in operation at IPPE since 1959 and has made it possible to obtain the first basic data on the physics, radioactive sodium technology, fuel element endurance, and other parameters needed to design the first sodium-cooled fast reactors. After it was upgraded in 1973 its capacity increased to 8MWt and is now referred to as BR-10. In 1983, essential reconstruction and vessel replacement significantly improved its safety and today it is used to investigate fuel endurance, study materials, and produce isotopes for biological and medical purposes. Various technical solutions to improve the safety of power reactors are verified and tested on BR-10, including experimental study of fission-product yield from failed fuel elements and study of structural material creepability. The facility provides continuous fast neutron and gamma irradiation and is also used for radioiso-tope production and treatment of cancer patients. Reactor life is being extended to the end of 2002 and the reactor will be decommissioned in 2003.
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