The Zero Power Physics Reactor or ZPPR (originally named Zero Power Plutonium Reactor) was a split-table-type critical facility located at the Idaho National Laboratory, Idaho, USA. [1] It was designed for the study of the physics of power breeder systems and was capable of simulating fast reactor core compositions characteristic of 300-500 MWe demonstration plants and 1000 MWe commercial plants. [2]
ZPPR ran only at extremely low power, for testing nuclear reactor designs. ZPPR was operated as a critical facility from April 18, 1969 until 1990.
The United States Atomic Energy Commission was engaged in funding and directing research and development in nuclear breeder reactors as a potential long-term energy source. Building a low-power critical mockup of a nuclear core is a common practice in advance of building a full-sized nuclear power plant of any novel design, especially in lieu of uncertain nuclear data. [3]
In 1964 development focus was shifting from small experimental reactors to large power-generating breeder reactors. The existing critical facilities (e.g. ZPR-3, ZPR-6, and ZPR-9) were too small and unprotected to handle the size of plutonium needed to simulate the core of a power breeder. Specifically, ZPR-3 could handle fast reactor plutonium experiments only up to a core volume of 600 liters, whereas ZPPR was designed to simulate systems with core volumes up to 5000 liters. [4] A plutonium inventory of 3000 kg was planned. [2]
The design basis accident (DBA) calculated to illustrate the capability of the containment structure included a reactivity insertion rate of 20 cents/second with complete failure of all safety devices. In this unlikely scenario, 40 kg of plutonium would have vaporized, and the sodium would have boiled and combusted with air. The associated toxicity concerns of this DBA necessitated the inclusion of the cell's gravel-sand roof and HEPA filters in the backup containment structure. [2]
In November, 1964 a $3 million contract was awarded to Mason & Hanger-Silas Mason Co to begin construction of the facility starting in late 1965.
Twenty-one major experimental campaigns were performed in the ZPPR facility between March, 1969 and September, 1990. Each campaign was designated with a number, from ZPPR-1 to ZPPR-21, including sub-designations for individual loadings within each campaign. The various experiments supported the Fast Flux Test Facility, the Clinch River Breeder Reactor Project, and the Integral fast reactor programs, among others. [3]
The data collected at ZPPR has been used regularly by nuclear reactor designers as a means to validate computer simulations. For example, in 2020 the Versatile Test Reactor program used ZPPR-15 to validate nuclear core calculations. [5]
In 2020, the National Reactor Innovation Center began developing two reactor demonstration test beds at Idaho National Laboratory, including one in the ZPPR cell, now known as the ZPPR Test bed (ZTB). [6]
Argonne National Laboratory is a federally funded research and development center in Lemont, Illinois, United States. Founded in 1946, the laboratory is owned by the United States Department of Energy and administered by UChicago Argonne LLC of the University of Chicago. The facility is the largest national laboratory by size and scope in the Midwest.
Experimental Breeder Reactor I (EBR-I) is a decommissioned research reactor and U.S. National Historic Landmark located in the desert about 18 miles (29 km) southeast of Arco, Idaho. It was the world's first breeder reactor. At 1:50 p.m. on December 20, 1951, it became one of the world's first electricity-generating nuclear power plants when it produced sufficient electricity to illuminate four 200-watt light bulbs. EBR-I subsequently generated sufficient electricity to power its building, and continued to be used for experimental purposes until it was decommissioned in 1964. The museum is open for visitors from late May until early September.
A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons, as opposed to slow thermal neutrons used in thermal-neutron reactors. Such a fast reactor needs no neutron moderator, but requires fuel that is relatively rich in fissile material when compared to that required for a thermal-neutron reactor. Around 20 land based fast reactors have been built, accumulating over 400 reactor years of operation globally. The largest of this was the Superphénix Sodium cooled fast reactor in France that was designed to deliver 1,242 MWe. Fast reactors have been intensely studied since the 1950s, as they provide certain decisive advantages over the existing fleet of water cooled and water moderated reactors. These are:
Idaho National Laboratory (INL) is one of the national laboratories of the United States Department of Energy and is managed by the Battelle Energy Alliance. While the laboratory does other research, historically it has been involved with nuclear research. Much of current knowledge about how nuclear reactors behave and misbehave was discovered at what is now Idaho National Laboratory. John Grossenbacher, former INL director, said, "The history of nuclear energy for peaceful application has principally been written in Idaho".
The integral fast reactor is a design for a nuclear reactor using fast neutrons and no neutron moderator. IFR would breed more fuel and is distinguished by a nuclear fuel cycle that uses reprocessing via electrorefining at the reactor site.
A molten salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant and/or the fuel is a mixture of molten salt with a fissionable material.
The BORAX Experiments were a series of safety experiments on boiling water nuclear reactors conducted by Argonne National Laboratory in the 1950s and 1960s at the National Reactor Testing Station in eastern Idaho. They were performed using the five BORAX reactors that were designed and built by Argonne. BORAX-III was the first nuclear reactor to supply electrical power to the grid in the United States in 1955.
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.
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 Dr. Vikram Sarabhai. Originally, it was called as Reactor Research Centre (RRC). It was renamed as 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.
The Argonaut class reactor is a design of small nuclear research reactor. Many have been built throughout the world, over a wide range of power levels. Its functions are to teach nuclear reactor theory, nuclear physics and for use in engineering laboratory experiments.
Generation IV reactors are nuclear reactor design technologies that are envisioned as successors of generation III reactors. The Generation IV International Forum (GIF) - an international organization that coordinates the development of generation IV reactors - specifically selected six reactor technologies as candidates for generation IV reactors. The designs target improved safety, sustainability, efficiency, and cost. The first commercial Gen IV plants are not expected before 2040–2050, although the World Nuclear Association in 2015 suggested that some might enter commercial operation before 2030.
A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.
The BN-350 is a sodium-cooled, fast reactor located at the Mangyshlak Nuclear Power Plant, located in Aktau, Kazakhstan, on the shore of the Caspian Sea.
PRISM is a nuclear power plant design by GE Hitachi Nuclear Energy (GEH).
The Materials Testing Reactor (MTR) was an early nuclear reactor specifically designed to facilitate the conception and 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.
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
Argonne Fast Source Reactor (AFSR) was a research reactor which was located at the Argonne National Laboratory, a United States Department of Energy national laboratory, facility located in the high desert of southeastern Idaho between Idaho Falls, Idaho and Arco, Idaho.
In Search of a Critical Moment — A 1970 film about the ZPPR