Project Pele is a project of the US Department of Defense to build a deployable nuclear power reactor [1] for use in United States Armed Forces remote operating bases.
In 2020 the project was listed as relevant to lunar and Mars missions. [2] : 15 presumably for surface operations rather than rocket propulsion.
On 9 March 2020, the Department awarded three development contracts, [3] to:
The two-year engineering design competition is for a small nuclear micro-reactor in the 1-5 megawatt (MWe) power range. [1]
Out of the initial three contracts - BWX Technologies, Westinghouse Government Services and X-energy - only BWX Technologies and X-energy were selected in 2021 to develop a final design for a prototype mobile microreactor under the Project Pele initiative [4] , and then in June 2022 BWXT was awarded a contract by the US Department of Defense (DOD) Strategic Capabilities Office (SCO) to build the prototype and deliver it by 2024. The estimated cost of this prototype is approximately 300 million USD [5] . In December 2022, BWXT started the TRISO fuel production at BWX Technologies Inc's Lynchburg facility in Virginia. [6]
The envisaged reactor is intended to be deployable by road, rail, aircraft, or sea. It will be capable of quickly being brought on load, and be inherently safe. [lower-alpha 1] Information from: US Army Futures Command
The pebble-bed reactor (PBR) is a design for a graphite-moderated, gas-cooled nuclear reactor. It is a type of very-high-temperature reactor (VHTR), one of the six classes of nuclear reactors in the Generation IV initiative.
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:
Atomic Energy of Canada Limited (AECL) is a Canadian federal Crown corporation and Canada's largest nuclear science and technology laboratory. AECL developed the CANDU reactor technology starting in the 1950s, and in October 2011 licensed this technology to Candu Energy.
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".
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 molten salt mixture. Only two MSRs have ever operated, both research reactors in the United States. The 1950's Aircraft Reactor Experiment was primarily motivated by the compact size that the technique offers, while the 1960's Molten-Salt Reactor Experiment aimed to prove the concept of a nuclear power plant which implements a thorium fuel cycle in a breeder reactor. Increased research into Generation IV reactor designs began to renew interest in the technology, with multiple nations having projects, and as of September 2021, China is on the verge of starting its TMSR-LF1 thorium MSR.
BWX Technologies, Inc., headquartered in Lynchburg, Virginia is a supplier of nuclear components and fuel to the U.S. On July 1, 2015, BWX Technologies Inc. began trading separately from its former subsidiary Babcock & Wilcox Enterprises Inc. after a spinoff. Sandy Baker became CEO and Fees became chairman. The company had 2,500 employees in Lynchburg and 4,500 in total.
Generation IV reactors are six nuclear reactor designs recognized by the Generation IV International Forum. The designs target improved safety, sustainability, efficiency, and cost.
A high-temperature gas-cooled reactor (HTGR), is a nuclear reactor that uses a graphite moderator with a once-through uranium fuel cycle. The HTGR is a type of high-temperature reactor (HTR) that can conceptually have an outlet temperature of 750 °C (1,380 °F). The reactor core can be either a "prismatic block" or a "pebble-bed" core. The high temperatures enable applications such as process heat or hydrogen production via the thermochemical sulfur–iodine cycle.
The lead-cooled fast reactor is a nuclear reactor design that features a fast neutron spectrum and molten lead or lead-bismuth eutectic coolant. Molten lead or lead-bismuth eutectic can be used as the primary coolant because especially lead, and to a lesser degree bismuth have low neutron absorption and relatively low melting points. Neutrons are slowed less by interaction with these heavy nuclei and therefore, help make this type of reactor a fast-neutron reactor. In simple terms, if a neutron hits a particle with a similar mass, it tends to lose kinetic energy. In contrast, if it hits a much heavier atom such as lead, the neutron will "bounce off" without losing this energy. The coolant does, however, serve as a neutron reflector, returning some escaping neutrons to the core. Fuel designs being explored for this reactor scheme include fertile uranium as a metal, metal oxide or metal nitride. Smaller capacity lead-cooled fast reactors can be cooled by natural convection, while larger designs use forced circulation in normal power operation, but will employ natural circulation emergency cooling. No operator interference is required, nor pumping of any kind to cool the residual heat of the reactor after shutdown. The reactor outlet coolant temperature is typically in the range of 500 to 600 °C, possibly ranging over 800 °C with advanced materials for later designs. Temperatures higher than 800 °C are theoretically high enough to support thermochemical production of hydrogen through the sulfur-iodine cycle, although this has not been demonstrated.
The Steam Generating Heavy Water Reactor (SGHWR) was a United Kingdom design for commercial nuclear reactors. It uses heavy water as the neutron moderator and normal "light" water as the coolant. The coolant boils in the reactor, like a boiling water reactor, and drives the power-extraction steam turbines.
North Korea (DPRK) has been active in developing nuclear technology since the 1950s.
As of 2022, nuclear power is provided by six commercial nuclear power plants in Pakistan. Pakistan is the first Muslim majority country in the world to construct and operate civil nuclear power plants. The Pakistan Atomic Energy Commission (PAEC), the scientific and nuclear governmental agency, is solely responsible for operating these power plants. As of 2018, the electricity generated by commercial nuclear power plants constitutes roughly 7.5% of electricity generated in Pakistan, Pakistan is not a party to the Nuclear Non-Proliferation Treaty but is a member of the International Atomic Energy Agency. Pakistan plans on constructing 32 nuclear power plants by 2050 and envisions 40,000 MW of nuclear power generation.
NuScale Power is a publicly traded American company that designs and markets small modular reactors (SMRs). It is headquartered in Tigard, Oregon, United States. NuScale has been approved to build reactors in Idaho, in 2029 and 2030. The design was approved for certification in July 2022.
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).
Small modular reactors (SMRs) are a proposed class of nuclear fission reactors, smaller than conventional nuclear reactors, which can be built in one location, then shipped, commissioned, and operated at a separate site. The term SMR refers to the size, capacity and modular construction only, not to the reactor type and the nuclear process which is applied. Designs range from scaled down versions of existing designs to generation IV designs. Both thermal-neutron reactors and fast-neutron reactors have been proposed, along with molten salt and gas cooled reactor models.
Centrus Energy Corp. is an American company that supplies nuclear fuel for use in nuclear power plants and works to develop and deploy advanced centrifuge technology to produce enriched uranium for commercial and government uses, including for national security.
X-energy is an American private nuclear reactor and fuel design engineering company. It is developing a Generation IV high-temperature gas-cooled pebble-bed nuclear reactor design. Since its founding in 2009, it has received various government grants and contracts, notably through the Department of Energy's (DOE) Advanced Reactor Concept Cooperative Agreement in 2016 and its Advanced Reactor Demonstration Program (ARDP) in 2020.
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
U-battery is a micro–small modular reactor design of a nuclear reactor.