Traveling wave reactor

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Numeric simulation of a TWR. Red: uranium-238, light green: plutonium-239, black: fission products. Intensity of blue color between the tiles indicates neutron density Laufwellenreaktor.gif
Numeric simulation of a TWR. Red: uranium-238, light green: plutonium-239, black: fission products. Intensity of blue color between the tiles indicates neutron density

A traveling-wave reactor (TWR) is a proposed type of nuclear fission reactor that can convert fertile material into usable fuel through nuclear transmutation, in tandem with the burnup of fissile material. TWRs differ from other kinds of fast-neutron and breeder reactors in their ability to use fuel efficiently without uranium enrichment or reprocessing, [ dubious – discuss ] instead directly using depleted uranium, natural uranium, thorium, spent fuel removed from light water reactors, or some combination of these materials. The concept is still in the development stage and no TWRs have ever been built.

Contents

The name refers to the fact that fission remains confined to a boundary zone in the reactor core that slowly advances over time. TWRs could theoretically run self-sustained for decades without refueling or removing spent fuel.

History

Traveling-wave reactors were first proposed in the 1950s and have been studied intermittently. The concept of a reactor that could breed its own fuel inside the reactor core was initially proposed and studied in 1958 by Savely Moiseevich Feinberg, who called it a "breed-and-burn" reactor. [1] Michael Driscoll published further research on the concept in 1979, [2] as did Lev Feoktistov in 1988, [3] Edward Teller/Lowell Wood in 1995, [4] Hugo van Dam in 2000 [5] and Hiroshi Sekimoto in 2001. [6]

The TWR was discussed at the Innovative Nuclear Energy Systems (INES) symposiums in 2004, 2006 and 2010 in Japan where it was called "CANDLE" Reactor, an abbreviation for Constant Axial shape of Neutron flux, nuclides densities and power shape During Life of Energy production. [7] In 2010 Popa-Simil discussed the case of micro-hetero-structures, [8] further detailed in the paper "Plutonium Breeding In Micro-Hetero Structures Enhances the Fuel Cycle", describing a TWR with deep burnout enhanced by plutonium [9] fuel channels and multiple fuel flow. In 2012 it was shown that fission [10] waves are a form of bi-stable reaction diffusion phenomenon. [11] It has also been shown that fission waves can be stable, unstable or undergo a Hopf birfurcation depending on thermal feedback. [12] Irradiation damage has been shown to be an obstacle to the use of conventional materials in wave reactor but in 2012 it was shown that fuel enrichment can be used to reduce this problem [13] and this was confirmed again in 2019. [14]

No TWR has yet been constructed, but in 2006 Intellectual Ventures launched a spin-off named TerraPower to model and commercialize a working design of such a reactor, which later came to be called a "traveling-wave reactor". TerraPower has developed TWR designs for low- to medium- (300 MWe) as well as high-power (~1000 MWe) generation facilities. [15] Bill Gates featured TerraPower in his 2010 TED talk. [16]

In 2010 a group from TerraPower applied for patent EP 2324480 A1 following WO2010019199A1 "Heat pipe nuclear fission deflagration wave reactor cooling". The application was deemed withdrawn in 2014. [17]

In September 2015 TerraPower and China National Nuclear Corporation (CNNC) signed a memorandum of understanding to jointly develop a TWR. TerraPower planned to build a 600 MWe demonstration Plant, the TWR-P, by 2018–2022 followed by larger commercial plants of 1150 MWe in the late 2020s. [18] However, in January 2019 it was announced that the project had been abandoned due to technology transfer limitations placed by the Trump administration. [19]

Reactor physics

Papers and presentations on TerraPower's TWR [20] [21] [22] describe a pool-type reactor cooled by liquid sodium. The reactor is fueled primarily by depleted uranium-238 "fertile fuel", but requires a small amount of enriched uranium-235 or other "fissile fuel" to initiate fission. Some of the fast-spectrum neutrons produced by fission are absorbed by neutron capture in adjacent fertile fuel (i.e. the non-fissile depleted uranium), which is "bred" into plutonium by the nuclear reaction:

Initially, the core is loaded with fertile material, with a few rods of fissile fuel concentrated in the central region. After the reactor is started, four zones form within the core: the depleted zone, which contains mostly fission products and leftover fuel; the fission zone, where fission of bred fuel takes place; the breeding zone, where fissile material is created by neutron capture; and the fresh zone, which contains unreacted fertile material. The energy-generating fission zone steadily advances through the core, effectively consuming fertile material in front of it and leaving spent fuel behind. Meanwhile, the heat released by fission is absorbed by the molten sodium and subsequently transferred into a closed-cycle aqueous loop, where electric power is generated by steam turbines. [21]

Fuel

TWRs use only a small amount (~10%) of enriched uranium-235 or other fissile fuel to "initiate" the nuclear reaction. The remainder of the fuel consists of natural or depleted uranium-238, which can generate power continuously for 40 years or more and remains sealed in the reactor vessel during that time. [22] TWRs require substantially less fuel per kilowatt-hour of electricity than do light-water reactors (LWRs), owing to TWRs' higher fuel burnup, energy density and thermal efficiency. A TWR also accomplishes most of its reprocessing within the reactor core. Spent fuel can be recycled after simple "melt refining", without the chemical separation of plutonium that is required by other kinds of breeder reactors. These features greatly reduce fuel and waste volumes while enhancing proliferation resistance. [21]

Depleted uranium is widely available as a feedstock. Stockpiles in the United States currently contain approximately 700,000 metric tons, which is a byproduct of the enrichment process. [23] TerraPower has estimated that the Paducah enrichment facility stockpile alone represents an energy resource equivalent to $100 trillion worth of electricity. [22] TerraPower has also estimated that wide deployment of TWRs could enable projected global stockpiles of depleted uranium to sustain 80% of the world's population at U.S. per capita energy usages for over a millennium. [24]

In principle, TWRs are capable of burning spent fuel from LWRs, which is currently discarded as radioactive waste. Spent LWR fuel is mostly low enriched uranium (LEU) and, in a TWR fast-neutron spectrum, the neutron absorption cross-section of fission products is several orders of magnitude smaller than in a LWR thermal-neutron spectrum. While such an approach could actually bring about an overall reduction in nuclear waste stockpiles, additional technical development is required to realize this capability.

TWRs are also capable, in principle, of reusing their own fuel. In any given cycle of operation, only 20–35% of the fuel gets converted to an unusable form; the remaining metal constitutes usable fissile material. Recast and reclad into new driver pellets without chemical separations, this recycled fuel can be used to initiate fission in subsequent cycles of operation, thus displacing the need to enrich uranium altogether.

The TWR concept is not limited to burning uranium with plutonium-239 as the "initiator" in a 238U–239Pu cycle, but may also burn thorium with uranium-233 as the "initiator" in a 232Th–233U cycle. [25]

Traveling wave vs. standing wave

The breed-burn wave in TerraPower's TWR design does not move from one end of the reactor to the other [26] but gradually from the center out. Moreover, as the fuel's composition changes through nuclear transmutation, fuel rods are continually reshuffled within the core to optimize the neutron flux and fuel usage over time. Thus, instead of letting the wave propagate through the fuel, the fuel itself is moved through a largely stationary burn wave. This is contrary to many media reports, [27] which have popularized the concept as a candle-like reactor with a burn region that moves down the length of a fuel section. By replacing a static core configuration with an actively managed "standing wave" or "soliton", however, TerraPower's design avoids the problem of cooling a moving burn region. Under this scenario, the reconfiguration of fuel rods is accomplished remotely by robotic devices; the containment vessel remains closed during the procedure, with no associated downtime.

Related Research Articles

<span class="mw-page-title-main">CANDU reactor</span> Canadian heavy water nuclear reactor design

The CANDU is a Canadian pressurized heavy-water reactor design used to generate electric power. The acronym refers to its deuterium oxide moderator and its use of uranium fuel. CANDU reactors were first developed in the late 1950s and 1960s by a partnership between Atomic Energy of Canada Limited (AECL), the Hydro-Electric Power Commission of Ontario, Canadian General Electric, and other companies.

<span class="mw-page-title-main">Nuclear reactor</span> Device used to initiate and control a nuclear chain reaction

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">Nuclear fuel cycle</span> Process of manufacturing and consuming nuclear fuel

The nuclear fuel cycle, also called nuclear fuel chain, is the progression of nuclear fuel through a series of differing stages. It consists of steps in the front end, which are the preparation of the fuel, steps in the service period in which the fuel is used during reactor operation, and steps in the back end, which are necessary to safely manage, contain, and either reprocess or dispose of spent nuclear fuel. If spent fuel is not reprocessed, the fuel cycle is referred to as an open fuel cycle ; if the spent fuel is reprocessed, it is referred to as a closed fuel cycle.

Mixed oxide fuel, commonly referred to as MOX fuel, is nuclear fuel that contains more than one oxide of fissile material, usually consisting of plutonium blended with natural uranium, reprocessed uranium, or depleted uranium. MOX fuel is an alternative to the low-enriched uranium fuel used in the light-water reactors that predominate nuclear power generation.

<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 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:

<span class="mw-page-title-main">Light-water reactor</span> Type of nuclear reactor that uses normal water

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.

<span class="mw-page-title-main">Integral fast reactor</span> Nuclear reactor design

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.

<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.

<span class="mw-page-title-main">Fertile material</span>

Fertile material is a material that, although not fissile itself, can be converted into a fissile material by neutron absorption.

<span class="mw-page-title-main">Plutonium-239</span> Isotope of plutonium

Plutonium-239 is an isotope of plutonium. Plutonium-239 is the primary fissile isotope used for the production of nuclear weapons, although uranium-235 is also used for that purpose. Plutonium-239 is also one of the three main isotopes demonstrated usable as fuel in thermal spectrum nuclear reactors, along with uranium-235 and uranium-233. Plutonium-239 has a half-life of 24,110 years.

<span class="mw-page-title-main">Sodium-cooled fast reactor</span> Type of nuclear reactor cooled by molten sodium

A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.

<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.

<span class="mw-page-title-main">Weapons-grade nuclear material</span> Nuclear material pure enough to be used for nuclear weapons

Weapons-grade nuclear material is any fissionable nuclear material that is pure enough to make a nuclear weapon or has properties that make it particularly suitable for nuclear weapons use. Plutonium and uranium in grades normally used in nuclear weapons are the most common examples.

Uranium-236 (236U) is an isotope of uranium that is neither fissile with thermal neutrons, nor very good fertile material, but is generally considered a nuisance and long-lived radioactive waste. It is found in spent nuclear fuel and in the reprocessed uranium made from spent nuclear fuel.

<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.

Hybrid nuclear fusion–fission is a proposed means of generating power by use of a combination of nuclear fusion and fission processes.

Reprocessed uranium (RepU) is the uranium recovered from nuclear reprocessing, as done commercially in France, the UK and Japan and by nuclear weapons states' military plutonium production programs. This uranium makes up the bulk of the material separated during reprocessing.

<span class="mw-page-title-main">TerraPower</span> Nuclear reactor design company

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 Energy Multiplier Module is a nuclear fission power reactor under development by General Atomics. It is a fast-neutron version of the Gas Turbine Modular Helium Reactor (GT-MHR) and is capable of converting spent nuclear fuel into electricity and industrial process heat.

References

  1. ↑ S. M. Feinberg, "Discussion Comment", Rec. of Proc. Session B-10, ICPUAE, United Nations, Geneva, Switzerland (1958).
  2. ↑ M. J. Driscoll, B. Atefi, D. D. Lanning, "An Evaluation of the Breed/Burn Fast Reactor Concept", MITNE-229 (Dec. 1979).
  3. ↑ L. P. Feoktistov, "An analysis of a concept of a physically safe reactor", Preprint IAE-4605/4, in Russian, (1988).
  4. ↑ E. Teller, M. Ishikawa, and L. Wood, "Completely Automated Nuclear Reactors for Long-Term Operation" (Part I), Proc. of the Frontiers in Physics Symposium, American Physical Society and the American Association of Physics Teachers Texas Meeting, Lubbock, Texas, United States (1995) ; Edward Teller, Muriel Ishikawa, Lowell Wood, Roderick Hyde, John Nuckolls, "Completely Automated Nuclear Reactors for Long-Term Operation II : Toward A Concept-Level Point-Design Of A High-Temperature, Gas-Cooled Central Power Station System (Part II)", Proc. Int. Conf. Emerging Nuclear Energy Systems, ICENES'96, Obninsk, Russia (1996) UCRL-JC-122708-RT2.
  5. ↑ H. van Dam, "The Self-stabilizing Criticality Wave Reactor", Proc. Of the Tenth International Conference on Emerging Nuclear Energy Systems (ICENES 2000), p. 188, NRG, Petten, Netherlands (2000).
  6. ↑ H. Sekimoto, K. Ryu, and Y. Yoshimura, "CANDLE: The New Burnup Strategy", Nuclear Science and Engineering, 139, 1–12 (2001).
  7. ↑ as proposed by Sekimoto in 2001 and 2005 published in Progress in Nuclear Energy
  8. ↑ "advanced Nuclear Reactor from Fiction to Reality", by Popa-Simil, published in the INES-3 proceeding
  9. ↑ L. Popa_Simil, Liviu. "Plutonium Futures Plutonium Breeding In Micro-Hetero Structures Enhances the Fuel Cycle". Plutonium Futures 2010. Archived from the original on 2020-01-21. Retrieved 2018-03-06.
  10. ↑ L. Popa-Simil. "Enhanced Singular Wave Reactor for Surface Power".
  11. ↑ A.G. Osborne, G.D. Recktenwald, M.R. Deinert, "Propagation of a solitary fission wave", Chaos, 22, 0231480 (2012).
  12. ↑ Osborne, Andrew G.; Deinert, Mark R. (October 2021). "Stability instability and Hopf bifurcation in fission waves". Cell Reports Physical Science. 2 (10): 100588. Bibcode:2021CRPS....200588O. doi: 10.1016/j.xcrp.2021.100588 .
  13. ↑ Osborne, AG, MR Deinert (2012): Neutron damage reduction in a traveling wave reactor.  Proceedings of Physor 2012, Knoxville, TN, April 15–20, 2012.
  14. ↑ Keckler, Chris; Fratoni, Massimiliano; Greenspan, Ehud (2020-11-01). "Sensitivity and Uncertainty Analysis of Neutron Spectrum and DPA in a B&B Core". Nuclear Science and Engineering. 194 (11): 1079–1088. Bibcode:2020NSE...194.1079K. doi:10.1080/00295639.2020.1715688. ISSN   0029-5639. S2CID   214281608.
  15. ↑ K. Weaver, C. Ahlfeld, J. Gilleland, C. Whitmer and G. Zimmerman, "Extending the Nuclear Fuel Cycle with Traveling-Wave Reactors", Paper 9294, Proceedings of Global 2009, Paris, France, September 6–11, (2009).
  16. ↑ Bill Gates. Innovating to zero!. TED . Retrieved 2010-07-13.
  17. ↑ Heat pipe nuclear fission deflagration wave reactor cooling , retrieved 2015-10-14
  18. ↑ World Nuclear News http://www.world-nuclear-news.org/NN-TerraPower-CNNC-team-up-on-travelling-wave-reactor-25091501.html
  19. ↑ Xuewan, Chen; Yelin, Mo; Tan, Jason; Ziwei, Tao (5 January 2019). "Nuclear Power Trial in China Will 'Not Proceed'". Caixin.
  20. ↑ R. Michal and E. M. Blake, "John Gilleland: On the traveling-wave reactor", Nuclear News, pp. 30–32, September (2009).
  21. 1 2 3 Wald, M. (February 24, 2009). "10 Emerging Technologies of 2009: Traveling-Wave Reactor". MIT Technology Review. Archived from the original on March 16, 2014. Retrieved April 12, 2018.
  22. 1 2 3 Gilleland, John (2009-04-20). TerraPower, LLC Nuclear Initiative. University of California at Berkeley, Spring Colloquium. Archived from the original on July 31, 2009. Retrieved April 12, 2018.
  23. ↑ United States Department of Energy, "Depleted UF6 Inventory and Storage Locations" Archived 2009-08-27 at the Wayback Machine . Accessed October 2009.
  24. ↑ L. Wood, T. Ellis, N. Myhrvold and R. Petroski, "Exploring The Italian Navigator's New World: Toward Economic, Full-Scale, Low Carbon, Conveniently-Available, Proliferation-Robust, Renewable Energy Resources", 42nd Session of the Erice International Seminars on Planetary Emergencies, Erice, Italy, 19024 August (2009).
  25. ↑ Rusov, V. D.; Linnik, E. P.; Tarasov, V. A.; Zelentsova, T. N.; Sharph, I. V.; Vaschenko, V. N.; Kosenko, S. I.; Beglaryan, M. E.; Chernezhenko, S. A.; Molchinikolov, P. A.; Saulenko, S. I.; Byegunova, O. A. (2011). "Traveling Wave Reactor and Condition of Existence of Nuclear Burning Soliton-Like Wave in Neutron-Multiplying Media". Energies. 4 (12): 1337. doi: 10.3390/en4091337 .
  26. ↑ T. Ellis; R. Petroski; P. Hejzlar; G. Zimmerman; D. McAlees; C. Whitmer; N. Touran; J. Hejzlar; K. Weaver; J. Walter; J. McWhirter; C. Alhfeld; T. Burke; A. Odedra; R. Hyde; J. Gilleland; Y. Ishikawa; L. Wood; N. Myrvold; W. Gates III (2010-06-14). Traveling-Wave Reactors: A Truly Sustainable and Full-Scale Resource for Global Energy Needs (PDF). American Nuclear Society, Summer Meeting. Retrieved April 12, 2018.
  27. ↑ M. Wald (2010-06-14). "Developer of Novel Reactor Wins $35 Million Infusion". The New York Times. Retrieved June 15, 2010.

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