U.S.-Russian Cooperation in Nuclear Energy: Part III
Friday, June 18th, 2010Part III: Efforts to Promote Research and Development of Fast Reactors
Fast neutron reactors (FNRs or fast reactors) which burn uranium more efficiently have a very high energy production rate compared to conventional power reactors. A fast breeder reactor (FBR) is designed to produce more plutonium than it consumes as fuel. According to the Argonne National Laboratory, “the fast reactor can create new fuel and destroy long-lived nuclear waste and plutonium while it produces electricity.”
The first U.S. prototype fast breeder reactor (Enrico Fermi, 66 MWe) operated for only three years and was shutdown for safety reasons in 1972. U.S. efforts to advance FNR technology have been constrained by several factors, including the high costs of building and operating prototype fast reactors, technical failures of the earliest reactor designs both in domestic programs and abroad, a lack of U.S. public support, and, most importantly, proliferation concerns due to “the plutonium content of the spent and reprocessed fuel.” U.S. research in the field of fast reactor technology continues, and there are now plans for the “deployment of prototype fast reactors between 2018 and 2025.” However, the lack of Congressional support and appropriations for advancing FNR technology has been criticized by supporters of nuclear energy.
Currently, Russia is the only country with an operating commercial fast reactor (BN-600, 600 MWe). According to the DOE Energy Information Administration, this reactor is “regarded as highly reliable.” France closed its remaining fast reactor (Phenix, 250 MWe, 1973-2009) last year. Japan has an experimental fast breeder reactor (Joyo, 140 MWt), which has been operating since 1977, and may restart a prototype fast breeder reactor (Monju, 280 MWe) in 2010. India has a fast breeder test reactor (FBTR, 40 MWt) which has been operating since 1985 and is constructing a prototype fast breeder reactor (PFBR, 500 MWe) scheduled for completion at the same location in 2011. Today’s critics of plutonium-fueled fast breeder reactors argue that Russia and India’s breeder reactor programs “leave much to be desired regarding the availability of data on reliability, safety and economics.”
Russia’s BN-600 reactor is a sodium-cooled fast breeder reactor (housed at Beloyarsk Unit 3) located at the Beloyarsk Nuclear Power Plant in the town of Zarechny, Sverdlovsk Oblast. It has been supplying electricity to the Middle Urals power grid since 1980 and “is said to have the best operating and production record of all Russia’s nuclear power units.” A large sodium leak in 1993 was reported to have had “negligible radiological consequences.” The BN-600 power unit was upgraded and received a license in April 2010 for 15 more years of operation.
Russia plans to commission the first BN-800 fast breeder reactor (housed at Beloyarsk Unit 4) in 2014. The new design of the more powerful (800 MWe) reactor offers fuel flexibility (U+Pu nitride, MOX, or metal fuels), enhanced safety, and improved operating costs.
Both the BN-600 and BN-800 reactors will be used in Russia to burn the country’s surplus weapons-grade plutonium as MOX fuel within the framework of the Plutonium Management and Disposition Agreement (PMDA). According to the bilateral agreement, they will be modified to dispose of plutonium “without creating new stocks of separated weapons-grade plutonium.”
In October 2009, Russia’s Atomstroyexport signed a contract to carry out pre-project work for construction of two power units with two BN-800 reactors in China. Construction of the first unit is scheduled to begin in 2011. The contract was concluded with the China Institute of Atomic Energy and with the China Nuclear Energy Industry Company.
Russia also has two lead-cooled fast reactor designs that can be applied commercially and are considered to be more proliferation resistant: the BREST fast reactor of 300 MWe and the Lead-Bismuth Fast Reactor (SVBR) of 100 MWe.
In 2008, Rosatom and Russian Machines set up a joint venture to design and build a prototype 100 MWe SVBR reactor. According to an Atomenergoprom presentation, the plan is to build the SVBR-100, test it, obtain licenses, and complete a new nuclear power plant with the SVBR technology by 2020. In 2009, Rosatom also set up a 50/50 joint venture with En+Group to design and produce a prototype SVBR reactor, as well as to obtain licenses. This pilot project is a public-private partnership. According to a Rosatom 2009 press release, the joint venture, OJSC AKME-engineering, is tasked with “completing R&D for the project.” The SVBR-100 reactor unit is “scheduled to be commissioned around 2019.”
Dr. Ehud Greenspan of the University of California, Berkeley, Department of Nuclear Engineering, suggests that the United States should consider basing an American prototype reactor on the Russian SVBR-100 technology and cooperating with Russia in further developing this lead-cooled fast reactor (LFR) technology.
Click here to read Part I of U.S.-Russian Cooperation in Nuclear Energy.
Click here to read Part II of U.S.-Russian Cooperation in Nuclear Energy.
