The Reed Research Reactor (RRR) ( 45°28′50″N122°37′48″W / 45.4806°N 122.6301°W ) is a research nuclear reactor located on-campus at Reed College in Portland, Oregon. It is a pool-type TRIGA Mark I reactor, built by General Atomics in 1968 and operated since then under licence from the Nuclear Regulatory Commission. Maximum thermal output is 250 kW. The reactor has over 1,000 visitors each year and serves the Reed College departments of Physics and Chemistry, as well as other departments. [1]
RRR is the only research reactor in the world that is owned and operated by an undergraduate educational institution. It is operated and maintained by undergraduate college students under the supervision of a director and operations manager who are members of the college staff. The facility provides scientific irradiation services to a broad community outside the college, but its primary mission is for student initiated research, training, and hands-on education.
The Reed Research Reactor is intended to produce thermal neutrons. It is used primarily for neutron activation to produce radioisotopes or analyze composition of material samples.
The RRR distinguishes itself from other university research reactors by the fact that it is one of the only reactors run completely by undergraduate students and serves undergraduate degree programs almost exclusively. Other reactors run by undergraduates include Idaho State University's AGN-201m, and University of New Mexico's AGN-201m. [2]
The facility is used in research projects, often conducted by the campus itself. As of November 2018, there are approximately 40 students licensed to operate the reactor. [3] In order to obtain such a license, students must attend a year of seminars on nuclear safety followed by an exam administered by the Nuclear Regulatory Commission. [4]
When the facilities were visited by ABC's "Radioactive Roadtrip" Primetime special, the fact that the school had no engineering program was purported as evidence that university reactors are sometimes kept as more of a status symbol than as a valid research tool. This is a quote from the ABC website:
University Reaction: The reactor is a "zero-risk facility," and there is no plausible way it is a threat, said Edward Hershey, director of public affairs at Reed College. Although the school has no nuclear engineering department – or any engineering department for that matter – chemistry and physics students use it as a resource. Hershey said the reactor is a "bragging point" for Reed. "It's just a neat facility," he said. [5]
The "zero-risk facility" comment reflects the reactor design which is a pin-type Low Enriched Uranium natural circulation driven Light Water Reactor, with a very strong negative temperature coefficient. As such, it is impossible to overheat the reactor, even in the case of a sudden reactivity insertion.
Irradiation facilities include equipment that is used to place, move, and organize samples that are to be irradiated.
The pneumatic transfer system (known colloquially as the "rabbit system") consists of an irradiation chamber in the outer ring of the core with its associated pump and piping. This allows samples to be transferred in and out of the reactor core very rapidly, while the reactor is at power. Routine use of the pneumatic transfer system involves placing samples into vials, which in turn are placed in special capsules known as "rabbits." The capsule is loaded into the system in the radiochemistry laboratory next to the reactor and is then transferred pneumatically into the core-irradiation position for a predetermined time. At the end of this period, the sample is transferred back to the receiving terminal, where it is removed for measurement. The transfer time from the core to the terminal is less than seven seconds, making this method of irradiating samples particularly useful for experiments involving radioisotopes with short half-lives. The flux in the core terminal is approximately 5×1012 n/cm2/s when the reactor is at full power.
The rotating specimen rack ( lazy susan ) is located in a well on top of the graphite reflector which surrounds the core. The rack consists of a circular array of 40 tubular receptacles. Each receptacle can accommodate two TRIGA-type irradiation tubes, so that up to 80 separate samples may be irradiated at any one time. Vials holding up to 17 millilitres (0.57 US fl oz) (2.57 centimetres (1.01 in) internal diameter, 10 centimetres (3.9 in) long) are routinely used in this system. Depending upon its geometry, a sample up to about 40 millilitres (1.4 US fl oz) could be irradiated by joining two vials. Samples are loaded in the specimen rack prior to the start-up of the reactor. The rack automatically rotates during irradiation to ensure each sample receives the same neutron flux. Typically, the rotating rack is used by researchers when longer irradiation times (generally greater than five minutes) are required. The average thermal neutron flux in the rotating rack position is approximately 2×1012 n/cm2/s with a cadmium ratio of 6.0 at full power. The specimen rack can also be used for gamma irradiations when the reactor is shut down. The shutdown gamma flux in the specimen rack is approximately 3 R/min.
The central thimble, which is a water-filled irradiation chamber about 3 centimetres (1.2 in) in diameter, provides the highest available neutron flux, about 1.4×1013 n/cm2/s. However, it holds only one specially positioned irradiation container, containing a cavity 7.5 centimetres (3.0 in) in length and 2.57 centimetres (1.01 in) in diameter.
Another in-core location is available by replacing one of the fuel elements with an irradiation chamber. The chamber fits into a fuel-element position within the core itself.
Foil-insertion holes, 0.79 centimetres (0.31 in) in diameter, are drilled at various positions through the grid plates. These holes allow inserting special holders containing flux wires into the core, to obtain neutron flux maps of the core.
Near core, in-pool irradiation facilities can be arranged for larger samples. Neutron fluxes will be lower than in the lazy susan and will depend on the sample location.
Neutron activation analysis (NAA) is a nuclear process used for determining the concentrations of elements in many materials. NAA allows discrete sampling of elements as it disregards the chemical form of a sample, and focuses solely on atomic nuclei. The method is based on neutron activation and thus requires a neutron source. The sample is bombarded with neutrons, causing its constituent elements to form radioactive isotopes. The radioactive emissions and radioactive decay paths for each element have long been studied and determined. Using this information, it is possible to study spectra of the emissions of the radioactive sample, and determine the concentrations of the various elements within it. A particular advantage of this technique is that it does not destroy the sample, and thus has been used for the analysis of works of art and historical artifacts. NAA can also be used to determine the activity of a radioactive sample.
A neutron source is any device that emits neutrons, irrespective of the mechanism used to produce the neutrons. Neutron sources are used in physics, engineering, medicine, nuclear weapons, petroleum exploration, biology, chemistry, and nuclear power. Neutron source variables include the energy of the neutrons emitted by the source, the rate of neutrons emitted by the source, the size of the source, the cost of owning and maintaining the source, and government regulations related to the source.
PLUTO was a materials testing nuclear reactor housed at the Atomic Energy Research Establishment, a former Royal Air Force airfield at Harwell, Oxfordshire in the United Kingdom.
The SLOWPOKE is a family of low-energy, tank-in-pool type nuclear research reactors designed by Atomic Energy of Canada Limited (AECL) beginning in the late 1960s. John W. Hilborn is the scientist most closely associated with their design. They are beryllium-reflected with a very low critical mass, but provide neutron fluxes higher than available from a small particle accelerator or other radioactive sources.
A swimming pool reactor, also called an open pool reactor, is a type of nuclear reactor that has a core immersed in an open pool usually of water.
The High Flux Isotope Reactor (HFIR) is a nuclear research reactor at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, United States. Operating at 85 MW, HFIR is one of the highest flux reactor-based sources of neutrons for condensed matter physics research in the United States, and it has one of the highest steady-state neutron fluxes of any research reactor in the world. The thermal and cold neutrons produced by HFIR are used to study physics, chemistry, materials science, engineering, and biology. The intense neutron flux, constant power density, and constant-length fuel cycles are used by more than 500 researchers each year for neutron scattering research into the fundamental properties of condensed matter. HFIR has about 600 users each year for both scattering and in-core research.
The International Fusion Materials Irradiation Facility, also known as IFMIF, is a projected material testing facility in which candidate materials for the use in an energy producing fusion reactor can be fully qualified. IFMIF will be an accelerator-driven neutron source producing a high intensity fast neutron flux with a spectrum similar to that expected at the first wall of a fusion reactor using a deuterium-lithium nuclear reaction. The IFMIF project was started in 1994 as an international scientific research program, carried out by Japan, the European Union, the United States, and Russia, and managed by the International Energy Agency. Since 2007, it has been pursued by Japan and the European Union under the Broader Approach Agreement in the field of fusion energy research, through the IFMIF/EVEDA project, which conducts engineering validation and engineering design activities for IFMIF. The construction of IFMIF is recommended in the European Roadmap for Research Infrastructures Report, which was published by the European Strategy Forum on Research Infrastructures (ESFRI).
North Carolina State University in 1950 founded the first university-based reactor program and Nuclear Engineering curriculum in the United States. The program continues in the early 21st century. That year, NC State College administrators approved construction of a reactor and the establishment of a collegiate nuclear engineering program. The first research reactor was completed in 1953; it was scaled up in 1957 and 1960. It was deactivated in 1973 to make way for the PULSTAR reactor. The old reactor has been decommissioned.
There are two nuclear research reactors that serve the Texas A&M University Nuclear Science Center. The older of the two is the AGN-201M model, a low-power teaching reactor. The newer reactor, the TRIGA Mark I, is focused strongly towards research.
The Oregon State University Radiation Center (OSURC) is a research facility that houses a nuclear reactor at Oregon State University (OSU) in Corvallis, Oregon, United States. The Oregon State TRIGA Reactor (OSTR) serves the research needs of the OSU nuclear engineering department along with other departments.
The University of Florida Training Reactor (UFTR), commissioned in 1959, is a 100 kW modified Argonaut-type reactor at the University of Florida in Gainesville, Florida. It is a light water and graphite moderated, graphite reflected, light water cooled reactor designed and used primarily for training and nuclear research related activities. The reactor is licensed by the Nuclear Regulatory Commission and is the only research reactor in Florida.
The Ford Nuclear Reactor was a facility at the University of Michigan in Ann Arbor dedicated to investigating the peaceful uses of nuclear power. It was a part of the Michigan Memorial Phoenix Project, a living memorial created to honor the casualties of World War II. The reactor operated from September 1957 until July 3, 2003. During its operation, the FNR was used to study medicine, cellular biology, chemistry, physics, mineralogy, archeology, anthropology, and nuclear science.
The Missouri University of Science and Technology Nuclear Reactor is a swimming pool type nuclear reactor operated by the Missouri University of Science and Technology. It first achieved criticality in 1961, making it the first operational nuclear reactor in the state of Missouri. Missouri S&T operates this reactor for training, education, and research purposes.
The Washington State University Reactor (WSUR) is housed in the Dodgen Research Facility, and was completed in 1961. The (then) Washington State College Reactor was the brainchild of Harold W. Dodgen, a former researcher on the Manhattan Project where he earned his PhD from 1943 to 1946. He secured funding for the ambitious 'Reactor Project' from the National Science Foundation, the Atomic Energy Commission, and the College administration totaling $479,000. Dodgen's basis for constructing a reactor was that the College was primely located as a training facility for the Hanford site, as well as Idaho National Laboratory because there was no other research reactor in the West at that time. After completing the extensive application and design process with the help of contractors from General Electric they broke ground in August 1957 and the first criticality was achieved on March 7, 1961 at a power level of 1W. They gradually increased power over the next year to achieve their maximum licensed operating power of 100 kW.
The Materials Testing Reactor (MTR) was an early nuclear reactor specifically designed to facilitate the conception and the design of future reactors. It produced much of the foundational irradiation data that underlies the nuclear power industry. It operated in Idaho at the National Reactor Testing Station from 1952 to 1970 and was fully decommissioned in 2011.
ETRR-1 or ET-RR-1, is the first nuclear reactor in Egypt supplied by the USSR in 1958. The reactor is owned and operated by Egyptian Atomic Energy Authority (AEA) at the Nuclear Research Center in Inshas, 40–60 kilometres (25–37 mi) northeast of Cairo.
ETRR-2 or ET-RR-2, or is the second nuclear reactor in Egypt supplied by the Argentine company Investigacion Aplicada (INVAP) in 1992. The reactor is owned and operated by Egyptian Atomic Energy Authority (EAEA) at the Nuclear Research Center in Inshas, 60 kilometres (37 mi) northeast of Cairo.
FiR 1 was Finland's first nuclear reactor. It was a research reactor that was located in the Otaniemi campus area in the city of Espoo. The TRIGA Mark II reactor had a thermal power of 250 kilowatts. It started operation in 1962, and it was permanently shut down in 2015. At first, the reactor was operated by Helsinki University of Technology (TKK), and since 1971 by VTT Technical Research Centre of Finland.
The Versatile Test Reactor (VTR) was a project by the U.S. Department of Energy to build a fast-neutron test reactor by 2026. Funding for the project was scrapped in 2022
Medical Research Reactor (MRR) was a research reactor which was located at Brookhaven National Laboratory, a United States Department of Energy national laboratory located in Upton, New York, on Long Island, approximately 60 miles east of New York City. The second of three reactors constructed at BNL, the MRR operated from 1959 until 2000 and has been partially decommissioned.
{{cite book}}: CS1 maint: location missing publisher (link)United States research reactors | ||
|---|---|---|
| Nuclear Regulatory Commission Licensed and operating research reactors (university-based) |
|  |
| U.S. company-operated research reactors |
| |
| U.S. National Labs with nuclear research reactors | ||