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 [1]
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 [1]
After the Fast Flux Test Facility and the Experimental Breeder Reactor-II (EBR-II) were decommissioned in 1992 and 1994, respectively, the United States was left with no fast-neutron reactor in its fleet. Fast-neutron research was limited to a few restricted reactors located in Russia, including the Bor-60. [2] To address this problem Nuclear Energy Innovation Capabilities Act of 2017 included a provision directing the Department of Energy to begin planning for a fast-neutron source. [3] Congress included $35 million in 2018 and $65 million in 2019 in the budget in support of this. In February 2019, VTR cleared Critical Decision 0, demonstrating a mission need requiring investment, the first in a series of project approvals. At that time, Secretary of Energy Rick Perry announced the start of the Versatile Test Reactor Project. [4] In November 2019, Battelle Energy Alliance, the organization that manages Idaho National Laboratory, announced an Expression of Interest (EOI) seeking an industry partner to design and construct the VTR. [5] In January 2020, a collaboration between GE Hitachi Nuclear Energy (GEH) and TerraPower supported by Energy Northwest was announced. [6] [7]
The potential building sites of the VTR being considered were Oak Ridge National Laboratory and Idaho National Laboratory. [8]
Funding for the project was scrapped in 2022 [9]
Four national laboratories, Idaho National Laboratory, Argonne National Lab, Los Alamos National Lab, and Oak Ridge National Laboratory worked with universities and commercial industry to come up with conceptual designs, costs and schedule estimates, and support. [10] [11]
The likely design will be a sodium-cooled 300 megawatt reactor based on GE-Hitachi’s PRISM reactor. The proposed first fuel will utilize a uranium-plutonium-zirconium alloy fuel. Such an alloy fuel was tested previously in the EBR-II reactor. Later reactor fuel could consist of other mixtures and varying enrichments of uranium and plutonium and could use other alloying metals in place of zirconium. [12] There are no power generating facilities planned for the VTR. [13]
The Department of Energy Office of Nuclear Energy (NE), Nuclear Energy Advisory Committee (NEAC) report, "Assessment of Missions and Requirements for a New U.S. Test Reactor" recommended the need for a US domestic fast-neutron test capability. The considerations for such a capability include [14]
These planned capabilities are roughly similar to the capabilities of the sodium-cooled fast neutron 400MWth test reactor Fast Flux Test Facility, located at the Hanford Site in the state of Washington, which was decommissioned in 1992.
The preliminary requirements that meet these considerations include:
Edwin Lyman, senior scientist and acting director of the Nuclear Safety Project at the non-profit Union of Concerned Scientists, questioned the need for a fast-neutron reactor, stating that existing facilities could be utilized to produce fast neutrons. [15] "There is nothing good about these reactors", he said. "I think there is a love of plutonium in the [Energy] Department that is irrational." [16]
The breeder design of the reactor produces more fissile material in the form of plutonium, resulting in proliferation fears.
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.
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. These reactors can be fueled with more-commonly available isotopes of uranium and thorium, such as uranium-238 and thorium-232, as opposed to the rare uranium-235 which is used in conventional reactors. These materials are called fertile materials since they can be bred into fuel by these breeder reactors.
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 advantages over the existing fleet of water cooled and water moderated reactors. These are:
The light-water reactor (LWR) is a type of thermal-neutron reactor that uses normal water, as opposed to heavy water, as both its coolant and neutron moderator; furthermore a solid form of fissile elements is used as fuel. Thermal-neutron reactors are the most common type of nuclear reactor, and light-water reactors are the most common type of thermal-neutron reactor.
The Fast Flux Test Facility (FFTF) is a 400 MW thermal, liquid sodium cooled, nuclear test reactor owned by the U.S. Department of Energy. It does not generate electricity. It is situated in the 400 Area of the Hanford Site, which is located in the state of Washington.
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.
Nuclear fuel is material used in nuclear power stations to produce heat to power turbines. Heat is created when nuclear fuel undergoes nuclear fission.
Generation IVreactors 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 World Nuclear Association in 2015 suggested that some might enter commercial operation before 2030.
The lead-cooled fast reactor is a nuclear reactor design that use molten lead or lead-bismuth eutectic coolant. These materials can be used as the primary coolant because they have low neutron absorption and relatively low melting points. Neutrons are slowed less by interaction with these heavy nuclei so these reactors operate with fast neutrons.
Experimental Breeder Reactor-II (EBR-II) was a sodium-cooled fast reactor designed, built and operated by Argonne National Laboratory at the National Reactor Testing Station in Idaho. It was shut down in 1994. Custody of the reactor was transferred to Idaho National Laboratory after its founding in 2005.
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.
A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.
A liquid metal cooled nuclear reactor, or LMR is a type of nuclear reactor where the primary coolant is a liquid metal. Liquid metal cooled reactors were first adapted for breeder reactor power generation. They have also been used to power nuclear submarines.
The Advanced Test Reactor (ATR) is a research reactor at the Idaho National Laboratory, located east of Arco, Idaho. This reactor was designed and is used to test nuclear fuels and materials to be used in power plants, naval propulsion, research and advanced reactors. It can operate at a maximum thermal power of 250 MW and has a "Four Leaf Clover" core design that allows for a variety of testing locations. The unique design allows for different neutron flux conditions in various locations. Six of the test locations allow an experiment to be isolated from the primary cooling system, providing its own environment for temperature, pressure, flow and chemistry, replicating the physical environment while accelerating the nuclear conditions.
PRISM is a nuclear power plant design by GE Hitachi Nuclear Energy (GEH).
TerraPower is an American nuclear reactor design and development engineering company headquartered in Bellevue, Washington. TerraPower is developing a class of nuclear fast reactors termed traveling wave reactors (TWR).
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.
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.