ThorCon nuclear reactor

Last updated
Artists impression of the TMSR-500 conceptual design. Thorcon isles power from shore.jpg
Artists impression of the TMSR-500 conceptual design.

The Thorcon nuclear reactor is a design of a molten salt reactor with a graphite moderator, proposed by the US-based Thorcon company. These nuclear reactors are designed as part of a floating power plant, to be manufactured on an assembly line in a shipyard, and to be delivered via barge to any ocean or major waterway shoreline, similar to the US's MH-1A from 1968 and the Russian Akademik Lomonosov operating since 2020. [1] The reactors are to be delivered as a sealed unit and never opened on site. All reactor maintenance and fuel processing is done at an off-site location. As of 2022, no reactor of this type has been built. A prototype of 500Mw (TMSR-500) output should be activated in Indonesia by 2029. [2]

Contents

Design

Raw material flows and waste at a ThorCon fuel processing plant. Enriched uranium powers the cycle, but most of the energy comes from the more abundant thorium. ThorCon Fuel Cycle.png
Raw material flows and waste at a ThorCon fuel processing plant. Enriched uranium powers the cycle, but most of the energy comes from the more abundant thorium.

ThorCon has proposed a power station closely based on the Molten-Salt Reactor Experiment in the 1960s, claiming that its design requires no new technology. The power station would contain two 250 MWe small modular reactors. The replaceable reactors are to be removed and replaced every four years. As molten salt reactors, they are designed for the use of fuel in liquid form, which also serves as primary coolant. [4] The fuel would be about 20% enriched uranium tetrafluoride and thorium tetrafluoride. The ThorCon design is a floating power station to be built in a shipyard and then towed to the location of operation. [5]

Safety

Thorcon claims that this reactor design will be safer than traditional nuclear reactors. The design includes several features intended to prevent meltdowns, contain radioactive materials, and protect from terrorism and sabotage.

Reviews

A 2017 study by the Energy Innovation Reform Project looked at the ThorCon and concluded that "if power plants featuring these technologies are able to produce electricity at the average LCOE price projected here (much less the low-end estimate), it would have a significant impact on electricity markets." [6]

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.

<span class="mw-page-title-main">Breeder reactor</span> Nuclear reactor generating more fissile material than it consumes

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.

<span class="mw-page-title-main">Fast-neutron reactor</span> Nuclear reactor where fast neutrons maintain a fission chain reaction

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 was the Superphénix sodium cooled fast reactor in France that was designed to deliver 1,242 MWe. Fast reactors have been studied since the 1950s, as they provide certain advantages over the existing fleet of water-cooled and water-moderated reactors. These are:

<span class="mw-page-title-main">Molten-salt reactor</span> Type of nuclear reactor cooled by molten material

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.

<span class="mw-page-title-main">Nuclear fuel</span> Material fuelling nuclear reactors

Nuclear fuel is material used in nuclear power stations to produce heat to power turbines. Heat is created when nuclear fuel undergoes nuclear fission. Nuclear fuel has the highest energy density of all practical fuel sources. The processes involved in mining, refining, purifying, using, and disposing of nuclear fuel are collectively known as the nuclear fuel cycle.

<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.

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.

<span class="mw-page-title-main">Thorium fuel cycle</span> Nuclear fuel cycle

The thorium fuel cycle is a nuclear fuel cycle that uses an isotope of thorium, 232
Th
, as the fertile material. In the reactor, 232
Th
is transmuted into the fissile artificial uranium isotope 233
U
which is the nuclear fuel. Unlike natural uranium, natural thorium contains only trace amounts of fissile material, which are insufficient to initiate a nuclear chain reaction. Additional fissile material or another neutron source is necessary to initiate the fuel cycle. In a thorium-fuelled reactor, 232
Th
absorbs neutrons to produce 233
U
. This parallels the process in uranium breeder reactors whereby fertile 238
U
absorbs neutrons to form fissile 239
Pu
. Depending on the design of the reactor and fuel cycle, the generated 233
U
either fissions in situ or is chemically separated from the used nuclear fuel and formed into new nuclear fuel.

The program for nuclear power in Indonesia includes plans to build nuclear reactors in the country for peaceful purposes. Indonesia prohibited development of nuclear weapon or any offensive uses due to signing the Treaty on the Non-Proliferation of Nuclear Weapons on 2 March 1970 and ratified it as Law No. 8/1978 on 18 December 1978.

<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.

The FUJI molten salt reactor is a proposed molten-salt-fueled thorium fuel cycle thermal breeder reactor, using technology similar to the Oak Ridge National Laboratory's Molten Salt Reactor Experiment – liquid fluoride thorium reactor. It was being developed by the Japanese company International Thorium Energy & Molten-Salt Technology (IThEMS), together with partners from the Czech Republic. As a breeder reactor, it converts thorium into the nuclear fuel uranium-233. To achieve reasonable neutron economy, the chosen single-salt design results in significantly larger feasible size than a two-salt reactor. Like all molten salt reactors, its core is chemically inert and under low pressure, helping to prevent explosions and toxic releases. The proposed design is rated at 200 MWe output. The IThEMS consortium planned to first build a much smaller MiniFUJI 10 MWe reactor of the same design once it had secured an additional $300 million in funding.

<span class="mw-page-title-main">Small modular reactor</span> Small nuclear reactors that could be manufactured in a factory and transported on site

Small modular reactors (SMRs) are a class of small nuclear fission reactors, designed to be built in a factory, shipped to operational sites for installation and then used to power buildings or other commercial operations. The first commercial SMR was invented by a team of nuclear scientists at Oregon State University (OSU) in 2007. Working with OSU's prototype, NuScale Power developed the first working model, available to the US market, in 2022. The term SMR refers to the size, capacity and modular construction. Reactor type and the nuclear processes may vary. Of the many SMR designs, the pressurized water reactor (PWR) is the most common. However, recently proposed SMR designs include: generation IV, thermal-neutron reactors, fast-neutron reactors, molten salt, and gas-cooled reactor models.

<span class="mw-page-title-main">Thorium-based nuclear power</span> Nuclear energy extracted from thorium isotopes

Thorium-based nuclear power generation is fueled primarily by the nuclear fission of the isotope uranium-233 produced from the fertile element thorium. A thorium fuel cycle can offer several potential advantages over a uranium fuel cycle—including the much greater abundance of thorium found on Earth, superior physical and nuclear fuel properties, and reduced nuclear waste production. One advantage of thorium fuel is its low weaponization potential. It is difficult to weaponize the uranium-233 that is bred in the reactor. Plutonium-239 is produced at much lower levels and can be consumed in thorium reactors.

<span class="mw-page-title-main">Integral Molten Salt Reactor</span>

The Integral Molten Salt Reactor (IMSR) is a nuclear power plant design targeted at developing a commercial product for the small modular reactor (SMR) market. It employs molten salt reactor technology which is being developed by the Canadian company Terrestrial Energy. It is based closely on the denatured molten salt reactor (DMSR), a reactor design from Oak Ridge National Laboratory. In addition, it incorporates some elements found in the SmAHTR, a later design from the same laboratory. The IMSR belongs to the DMSR class of molten salt reactors (MSR) and hence is a "burner" reactor that employs a liquid fuel rather than a conventional solid fuel. This liquid contains the nuclear fuel as well as serving as the primary coolant.

Transatomic Power was an American company that designed Generation IV nuclear reactors based on molten salt reactor (MSR) technology.

<span class="mw-page-title-main">Stable salt reactor</span>

The Stable Salt Reactor (SSR) is a nuclear reactor design under development by Moltex Energy Canada Inc. and its subsidiary Moltex Energy USA LLC, based in Canada, the United States, and the United Kingdom, as well as MoltexFLEX Ltd., based in the United Kingdom.

Seaborg Technologies is a private Danish startup. It is developing small molten salt reactors. Founded in 2015 and based in Copenhagen, Denmark, Seaborg emerged as a small team of physicists, chemists, and engineers with educational roots at the Niels Bohr Institute, CERN, ESS and DTU who share a common vision of safe, sustainable and cheap nuclear power.

Copenhagen Atomics is a Danish molten salt technology company developing mass manufacturable molten-salt reactors. The company is pursuing small modular, molten fuel salt, thorium fuel cycle, thermal spectrum, breeder reactors using separated plutonium from spent nuclear fuel as the initial fissile load for the first generation of reactors.

<span class="mw-page-title-main">TMSR-LF1</span> Molten salt reactor prototype

TMSR-LF1 is a 2 MWt molten salt reactor (MSR) pilot plant located in northwest China.

References

  1. Patel, Sonal (2023-02-01). "Floating Nuclear Power Buoyant on New Prospects". Power Magazine.
  2. World Nuclear News: ThorCon begins pre-licensing consultation in Indonesia
  3. ThorCon Fuel Cycle
  4. Design. ThorCon webpage (retrieved April 2022)
  5. Status Report – ThorCon (Thorcon US, Inc.) USA/Indonesia, 22 June 2020
  6. EIRP (July 2017). "What Will Advanced Nuclear Plants Cost?". Archived from the original on 2022-04-16. Retrieved 2020-01-06.