Purdue University Reactor Number One

Last updated
Purdue University Reactor Number One
PUR-1.jpg
The PUR-1 cooling pool
USA Indiana location map.svg
Red pog.svg
Location of Purdue University Reactor Number One
Operating Institution Purdue University
Location West Lafayette, Indiana, USA
Coordinates 40°25′42″N86°54′41″W / 40.42833°N 86.91139°W / 40.42833; -86.91139
Type Open pool reactor
Power10 kW (thermal)
Construction and Upkeep
Construction Cost$125,000
Construction Began1961 (1961)
First CriticalityAugust 30, 1962 [1]
Annual Upkeep Cost$7,000
Staff3
Operators3
Technical Specifications
Max Thermal Flux 2.1×1010 n/cm2·s
Max Fast Flux 1.2×1010 n/cm2·s
Fuel TypeFlat plate MTR [1]
Cooling Light water
Neutron Moderator Light water
Neutron Reflector Graphite
Control Rods3
Cladding MaterialAluminum alloy
Source(s): "PUR-1 Purdue Univ". International Atomic Energy Agency. September 17, 1998. Retrieved October 6, 2012.

The Purdue University Reactor Number One (PUR-1) is a research reactor in West Lafayette, Indiana, United States. It is used primarily for teaching purposes in Purdue University's School of Nuclear Engineering. Built in 1962, the PUR-1 is the only nuclear reactor operating in the US state of Indiana. It was the second reactor installed in Indiana, and was the first critical reactor, after a sub-critical reactor was installed at Valparaiso University in 1958. [2]

Contents

Design

In April 1961, Purdue University selected Lockheed Corporation to build its research reactor after twelve companies submitted bids. [3] It was installed underground, three stories beneath the Duncan Annex of Purdue's Electrical Engineering Building. [4] [5] The reactor first achieved criticality on August 30, 1962, and a dedication ceremony was held on September 27 of that year. [1] [6] The construction cost was $125,000. [6]

The PUR-1 was the second nuclear reactor and first critical reactor in Indiana. [3] A third reactor was later installed at the planned Marble Hill Nuclear Power Plant in Jefferson County but was removed when construction of the plant halted in 1984. The reactor at Valparaiso University was dismantled in 2000. As a result, the PUR-1 is currently the only reactor in the state. [7]

The Purdue reactor was among the first to be designed mainly for student use. [3] It is licensed to produce up to one kilowatt of thermal power, comparable to the energy demand of a hair dryer or a toaster. [4] This low power makes it safer and less expensive than reactors designed for research or electricity generation. [3] The reactor's core is 2 cubic feet (0.057 m3) in volume and sits at the bottom of a 17-foot-deep (5.2 m) cooling pool of water that measures 8 feet (2.4 m) in diameter. [4] This allows the core to be safely viewed while it is operating. [3]

Use

The reactor's primary purpose is for training students in the principles of reactor physics. [1] [4] The university also uses it as a source for neutrons for research in nuclear engineering, health science, chemistry, pharmacy, agriculture, biology, and nanotechnology. [8]

Purdue's reactor is also used for outreach. The School of Nuclear Engineering regularly gives tours of its facilities to local high school students and the general public. As of 2012, it was estimated that between 1,600 and 1,800 visitors see the reactor facilities annually. [4]

Safety

In 2005, journalism interns produced a report for ABC News about the possibility of terrorist attacks on research reactors in the United States. When they arrived at Purdue University, the interns were surprised at how easy it was for the general public to obtain a tour of the reactor facilities. They also noted a lack of background checks, guards, and metal detectors. [9]

In response, the university said that the ABC report had misrepresented the nature of research reactors and that the interns were not qualified to make such safety evaluations. Unlike power plants, that produce electricity by running steam turbines, research reactors operate well below boiling conditions. Because of its low power range and its underground location, Purdue says that any attack on its reactor facilities would be unlikely to affect anything outside of that room. The way in which the reactor is installed means that theft of its fuel would require "a major construction project" that "could not be done covertly." [5]

The PUR-1 originally used highly enriched, or "weapons-grade", uranium as fuel. In 1982, the government announced plans to convert civilian reactors to low-enriched uranium. [10] Conversion of the Purdue reactor was completed in September 2007. [11]

On February 16, 2021, the NRC issued a Notice of Violation to Purdue University involving two violations. The first violation involves the Purdue University Research Reactor operating at steady state power levels in excess of 12 kilowatts (thermal) on several occasions between October 31, 2019, and September 15, 2020, which was beyond allowed thermal power levels as limited in their Reactor License. Specifically, the reactor was inadvertently operated at power levels greater than 12 kW(t) during this time due to nuclear instrument (NI) calibration calculation errors that caused the NIs to indicate reactor power levels that were approximately three times lower than actual reactor power. Therefore, when the licensee operated the reactor above 4 kW(t) (indicated power) several times between October 31, 2019, and September 15, 2020, the actual reactor power exceeded the maximum authorized power level of 12 kW(t). The second violation involves Purdue University’s failure to perform appropriate surveillance testing before considering the NI system operable following replacement of the NI system and detectors in 2019. [12]

See also

Related Research Articles

<span class="mw-page-title-main">Nuclear reactor</span> Device for controlled nuclear reactions

A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction or nuclear fusion reactions. Nuclear reactors are used at nuclear power plants for electricity generation and in nuclear marine propulsion. Heat from nuclear fission is passed to a working fluid, which in turn runs through steam turbines. These either drive a ship's propellers or turn electrical generators' shafts. Nuclear generated steam in principle can be used for industrial process heat or for district heating. Some reactors are used to produce isotopes for medical and industrial use, or for production of weapons-grade plutonium. As of 2022, the International Atomic Energy Agency reports there are 422 nuclear power reactors and 223 nuclear research reactors in operation around the world.

Enriched uranium is a type of uranium in which the percent composition of uranium-235 has been increased through the process of isotope separation. Naturally occurring uranium is composed of three major isotopes: uranium-238, uranium-235, and uranium-234. 235U is the only nuclide existing in nature that is fissile with thermal neutrons.

<span class="mw-page-title-main">Nuclear and radiation accidents and incidents</span> Severe disruptive events involving fissile or fusile materials

A nuclear and radiation accident is defined by the International Atomic Energy Agency (IAEA) as "an event that has led to significant consequences to people, the environment or the facility." Examples include lethal effects to individuals, large radioactivity release to the environment, or a reactor core melt. The prime example of a "major nuclear accident" is one in which a reactor core is damaged and significant amounts of radioactive isotopes are released, such as in the Chernobyl disaster in 1986 and Fukushima nuclear disaster in 2011.

The S1W reactor was the first prototype naval reactor used by the United States Navy to prove that the technology could be used for electricity generation and propulsion on submarines.

<span class="mw-page-title-main">Shippingport Atomic Power Station</span> Atomic electricity plant in the US

The Shippingport Atomic Power Station was the world's first full-scale atomic electric power plant devoted exclusively to peacetime uses. It was located near the present-day Beaver Valley Nuclear Generating Station on the Ohio River in Beaver County, Pennsylvania, United States, about 25 miles (40 km) from Pittsburgh.

<span class="mw-page-title-main">Bhabha Atomic Research Centre</span> Nuclear research facility in Mumbai, India

The Bhabha Atomic Research Centre (BARC) is India's premier nuclear research facility, headquartered in Trombay, Mumbai, Maharashtra, India. It was founded by Homi Jehangir Bhabha as the Atomic Energy Establishment, Trombay (AEET) in January 1954 as a multidisciplinary research program essential for India's nuclear program. It operates under the Department of Atomic Energy (DAE), which is directly overseen by the Prime Minister of India.

<span class="mw-page-title-main">Indira Gandhi Centre for Atomic Research</span> Indias premier nuclear research centre

Indira Gandhi Centre for Atomic Research (IGCAR) is one of India's premier nuclear research centres. It is the second largest establishment of the Department of Atomic Energy (DAE), next to Bhabha Atomic Research Centre (BARC), located at Kalpakkam, 80 km south of Chennai, India. It was established in 1971 as an exclusive centre dedicated to the pursuit of fast reactor science and technology, due to the vision of Vikram Sarabhai. Originally, it was called Reactor Research Centre (RRC). It was renamed to Indira Gandhi Centre for Atomic Research (IGCAR) by the then Prime Minister of India Rajiv Gandhi in December 1985. The centre is engaged in broad-based multidisciplinary programme of scientific research and advanced engineering directed towards the development of fast breeder reactor technology in India.

<span class="mw-page-title-main">Aqueous homogeneous reactor</span> Type of nuclear reactor

Aqueous homogeneous reactors (AHR) is a two (2) chamber reactor consisting of an interior reactor chamber and an outside cooling and moderating jacket chamber. They are a type of nuclear reactor in which soluble nuclear salts are dissolved in water. The fuel is mixed with heavy or light water which partially moderates and cools the reactor. The outside layer of the reactor has more water which also partially cools and acts as a moderator. The water can be either heavy water or ordinary (light) water, which slows neutrons and helps facilitate a stable reaction, both of which need to be very pure.

<span class="mw-page-title-main">SLOWPOKE reactor</span> Family of nuclear research reactors

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.

<span class="mw-page-title-main">Reed Research Reactor</span>

The Reed Research Reactor (RRR) 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.

The advanced heavy-water reactor (AHWR) or AHWR-300 is the latest Indian design for a next-generation nuclear reactor that burns thorium in its fuel core. It is slated to form the third stage in India's three-stage fuel-cycle plan. This phase of the fuel cycle plan was supposed to be built starting with a 300 MWe prototype in 2016.

<span class="mw-page-title-main">X-10 Graphite Reactor</span> Decommissioned nuclear reactor in Tennessee

The X-10 Graphite Reactor is a decommissioned nuclear reactor at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Formerly known as the Clinton Pile and X-10 Pile, it was the world's second artificial nuclear reactor and the first designed and built for continuous operation. It was built during World War II as part of the Manhattan Project.

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 University of Missouri Research Reactor Center (MURR) is home to a tank-type nuclear research reactor that serves the University of Missouri in Columbia, United States. As of March 2012, the MURR is the highest-power university research reactor in the U.S. at 10 megawatt thermal output. The fuel is highly enriched uranium.

<span class="mw-page-title-main">UF Training Reactor</span>

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.

<span class="mw-page-title-main">MIT Nuclear Research Reactor</span> Research nuclear reactor

The MIT Nuclear Research Reactor (MITR) serves the research purposes of the Massachusetts Institute of Technology. It is a tank-type 6 megawatt reactor that is moderated and cooled by light water and uses heavy water as a reflector. It is the second largest university-based research reactor in the U.S. and has been in operation since 1958. It is the fourth-oldest operating reactor in the country.

<span class="mw-page-title-main">Liquid fluoride thorium reactor</span> Type of nuclear reactor that uses molten material as fuel

The liquid fluoride thorium reactor is a type of molten salt reactor. LFTRs use the thorium fuel cycle with a fluoride-based molten (liquid) salt for fuel. In a typical design, the liquid is pumped between a critical core and an external heat exchanger where the heat is transferred to a nonradioactive secondary salt. The secondary salt then transfers its heat to a steam turbine or closed-cycle gas turbine.

<span class="mw-page-title-main">Missouri University of Science and Technology Nuclear Reactor</span> Open pool nuclear reactor

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.

A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water (deuterium oxide D2O) as its coolant and neutron moderator. PHWRs frequently use natural uranium as fuel, but sometimes also use very low enriched uranium. The heavy water coolant is kept under pressure to avoid boiling, allowing it to reach higher temperature (mostly) without forming steam bubbles, exactly as for a pressurized water reactor. While heavy water is very expensive to isolate from ordinary water (often referred to as light water in contrast to heavy water), its low absorption of neutrons greatly increases the neutron economy of the reactor, avoiding the need for enriched fuel. The high cost of the heavy water is offset by the lowered cost of using natural uranium and/or alternative fuel cycles. As of the beginning of 2001, 31 PHWRs were in operation, having a total capacity of 16.5 GW(e), representing roughly 7.76% by number and 4.7% by generating capacity of all current operating reactors.

<span class="mw-page-title-main">FiR 1</span>

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.

References

  1. 1 2 3 4 Bean, R.S.; Merritt, E.C. (February 22, 2000). Perez, Pedro B. (ed.). "Purdue University". University Research Reactors: Contributing to the National Scientific and Engineering Infrastructure from 1953 to 2000 and Beyond. National Organization of Test, Research and Training Reactors. Archived from the original on July 1, 2007. Retrieved October 6, 2012.
  2. "The End of an Era: The Uranium is Gone". December 2000.
  3. 1 2 3 4 5 "First in State: Purdue to Get Nuclear Reactor". The Rochester Sentinel. Rochester, Indiana. April 24, 1961. p. 1. Retrieved October 6, 2012.
  4. 1 2 3 4 5 Hamon, Amanda (September 25, 2012). "Did You Know?: Purdue Reactor No. 1". Purdue University. Retrieved October 6, 2012.
  5. 1 2 Tsoukalas, Lefteri (October 14, 2005). "Commentary on ABC's nuclear report". Purdue University. Retrieved October 6, 2012.
  6. 1 2 "Purdue Dedicates Atomic Furnace". Warsaw Times-Union. Warsaw, Indiana. Associated Press. September 28, 1962. p. 10. Retrieved October 6, 2012.
  7. "Indiana". Nuclear Regulatory Commission. May 17, 2012. Retrieved October 6, 2012.
  8. "Purdue: University's nuclear reactor safe, federal guidelines followed". Purdue University. October 14, 2005. Retrieved October 6, 2012.
  9. "Purdue University". ABC News. November 9, 2005. Retrieved October 6, 2012.
  10. "Guidelines forthcoming to halt use in colleges of bomb-grade uranium". St. Joseph News-Press/Gazette. St. Joseph, Missouri. Associated Press. January 28, 1984. p. 10C. Retrieved October 6, 2012.
  11. "NNSA Successfully Converts Third Domestic Research Reactor in the Last Year". National Nuclear Security Administration. September 13, 2007. Retrieved September 2, 2013.
  12. "Purdue University (Purdue University Research Reactor) (EA-20-144)" (PDF). February 16, 2021.