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Transient Reactor Test Facility (TREAT)
The Transient Reactor Test Facility (TREAT) is an air-cooled, graphite moderated, thermal spectrum test nuclear reactor designed to test reactor fuels and structural materials. Constructed in 1958, and operated from 1959 until 1994, TREAT was built to conduct transient reactor tests where the test material is subjected to neutron pulses that can simulate conditions ranging from mild transients to a reactor accidents. TREAT was designed by Argonne National Laboratory, and is located at the Idaho National Laboratory. Since original construction, the facility had additions or systems upgrades in 1963, 1972, 1982, and 1988. The 1988 addition was extensive, and included upgrades of most of the instrumentation and control systems.〔(【引用サイトリンク】url=http://www4vip.inl.gov/research/transient-reactor-test-facility/ )〕
The U.S. Department of Energy (DOE) has decided to resume a program of transient testing,〔(【引用サイトリンク】url=http://www.energy.gov/em/articles/doe-issues-finding-no-significant-impact-environmental-assessment-resumption-transient )〕〔(【引用サイトリンク】url=http://www.energy.gov/ne/articles/resumption-transient-testing )〕〔(【引用サイトリンク】website = Snake River Alliance )〕 and plans to invest about $75 million to restart the TREAT facility by 2018. The renewed interest in TREAT was sparked by the 2011 Fukushima Daiichi nuclear disaster, which prompted the shutdown of Japan's and Germany's nuclear plants. One use for TREAT is planned to be testing of new accident tolerant fuel for nuclear reactors.〔(【引用サイトリンク】url=http://www.energy.gov/ne/downloads/development-light-water-reactor-fuels-enhanced-accident-tolerance-report-congress )〕
==Fuel and Core Description==
The TREAT fuel assemblies are approximately 9 feet long, and 4 inches square in cross section. The fuel is a graphite uranium mixture, with 1 part uranium to 10,000 parts graphite. The active portion of the fuel assembly is about 48 inches, with a graphite reflector of about 24 inches above and below the active portion. The active portion of the fuel assemblies are encased with Zircaloy. There is also a graphite axial reflector, composed of two parts. The first part of the axial reflector consists of movable assemblies similar to the fuel assemblies, but containing only graphite and no fuel. The second part of the axial reflector consists of permanent blocks of graphite, approximately 24 inches thick, stacked outside the core cavity. This permanent reflector was reclaimed from Chicago Pile-1, the world's first nuclear reactor. The core may be loaded to a size of 5 feet by 5 feet (nominal) up to 6 feet by 6 feet (maximum), depending on the needs of the experiment.〔
As described above, the fuel is composed of a mixture of graphite and uranium. The uranium is in the form of uranium oxide particles that are approximately 20 micron in size, and are in direct contact with the graphite moderator. The graphite, in addition to being the neutron moderator, also acts as a large thermal heat sink. The time lag of the heat transfer is on the order of 1 millisecond, much faster than the heat transfer to a liquid coolant flowing past fuel assemblies. Also, when the graphite is heated it creates a sizable negative moderator temperature coefficient. These characteristics allow TREAT to produce large ‘self-limited’ transients, which are limited by the fuel negative moderator coefficient without control rod movement.
抄文引用元・出典: フリー百科事典『 ウィキペディア（Wikipedia）』
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