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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, 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.

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.

Laufwellenreaktor

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

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]

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.[12] Bill Gates featured TerraPower in his 2010 TED talk.[13]

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.[14]

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.[15] However, in January 2019 it was announced that the project had been abandoned due to technology transfer limitations placed by the Trump administration.[16]

Reactor physics

Papers and presentations on TerraPower's TWR[17][18][19] 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:

\( \mathrm{^{238}_{\ 92}U + \,^{1}_{0}n \;\rightarrow\; ^{239}_{\ 92}U \;\rightarrow\; ^{239}_{\ 93}Np + \beta \;\rightarrow\; ^{239}_{\ 94}Pu + \beta} \)

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.[18]

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.[19] 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.[18]

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.[20] TerraPower has estimated that the Paducah enrichment facility stockpile alone represents an energy resource equivalent to $100 trillion worth of electricity.[19] 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.[21]

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.[22]
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[23] 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,[24] which have popularized the concept as a candle-like reactor with a burn region that moves down a stick of fuel. 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.

References

S. M. Feinberg, "Discussion Comment", Rec. of Proc. Session B-10, ICPUAE, United Nations, Geneva, Switzerland (1958).
M. J. Driscoll, B. Atefi, D. D. Lanning, "An Evaluation of the Breed/Burn Fast Reactor Concept", MITNE-229 (Dec. 1979).
L. P. Feoktistov, "An analysis of a concept of a physically safe reactor", Preprint IAE-4605/4, in Russian, (1988).
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.
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).
H. Sekimoto, K. Ryu, and Y. Yoshimura, "CANDLE: The New Burnup Strategy", Nuclear Science and Engineering, 139, 1–12 (2001).
as proposed by Sekimoto in 2001 and 2005 published in Progress in Nuclear Energy
"advanced Nuclear Reactor from Fiction to Reality", by Popa-Simil, published in the INES-3 proceeding
L. Popa_Simil, Liviu. "Plutonium Futures Plutonium Breeding In Micro-Hetero Structures Enhances the Fuel Cycle". Plutonium Futures 2010.
L. Popa-Simil. "Enhanced Singular Wave Reactor for Surface Power".
A.G. Osborne, G.D. Recktenwald, M.R. Deinert, "Propagation of a solitary fission wave", Chaos, 22, 0231480 (2012).
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).
Bill Gates. Innovating to zero!. TED. Retrieved 2010-07-13.
Heat pipe nuclear fission deflagration wave reactor cooling, retrieved 2015-10-14
World Nuclear News http://www.world-nuclear-news.org/NN-TerraPower-CNNC-team-up-on-travelling-wave-reactor-25091501.html
Xuewan, Chen; Yelin, Mo; Tan, Jason; Ziwei, Tao (5 January 2019). "Nuclear Power Trial in China Will 'Not Proceed'". Caixin.
R. Michal and E. M. Blake, "John Gilleland: On the traveling-wave reactor", Nuclear News, pp. 30–32, September (2009).
Wald, M. (February 24, 2009). "10 Emerging Technologies of 2009: Traveling-Wave Reactor". MIT Technology Review. Retrieved April 12, 2018.
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.
United States Department of Energy, "Depleted UF6 Inventory and Storage Locations" Archived 2009-08-27 at the Wayback Machine. Accessed October 2009.
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).
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.
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.

M. Wald (2010-06-14). "Developer of Novel Reactor Wins $35 Million Infusion". The New York Times. Retrieved June 15, 2010.

Further reading

Arjun Makhijani (September 2013), "Traveling Wave Reactors: Sodium-cooled Gold at the End of a Nuclear Rainbow?", Institute for Energy and Environmental Research.

External links

"TerraPower Reactors Approach the Nuclear Ideal" by Intellectual Ventures Lab.
TerraPower: How The Traveling Wave Nuclear Reactor Works, inc 4 diagrams from IV.
Terrapower.com company website
Rusov, V. D.; Tarasov, V. A.; Sharf, I. V.; Vaschenko, V. M.; Linnik, E. P.; Zelentsova, T. N.; Beglaryan, M. E.; Chernegenko, S. A.; Kosenko, S. I.; Smolyar, V. P. (2012). "On some fundamental peculiarities of the traveling wave reactor". Science and Technology of Nuclear Installations. 2015: 1–23. arXiv:1207.3695. Bibcode:2012arXiv1207.3695R. doi:10.1155/2015/703069.

vte

Types of nuclear fission reactor
Moderator
Light water

Aqueous homogeneous Boiling
BWR ABWR ESBWR Kerena Pressurized
AP1000 APR-1400 APR+ APWR ATMEA1 CAP1400 CPR-1000 EPR HPR-1000
ACPR1000 ACP1000 VVER many others Supercritical (SCWR) Natural fission

Heavy water
D2O

Pressurized
CANDU
CANDU 6 CANDU 9 EC6 AFCR ACR-1000 AHWR CVTR IPHWR-X PHWR KWU MZFR R3 R4 Marviken

H2O

HWLWR
ATR HW BLWR 250 Steam-generating (SGHWR)

Organic

WR-1

CO2

HWGCR
EL-4 KKN KS 150 Lucens

Graphite 
by coolant

Water
H2O

AM-1 AMB-X EGP-6 RBMK

Gas
CO2

Uranium Naturel Graphite Gaz (UNGG) Magnox Advanced gas-cooled (AGR)

He

GTMHR
MHR-T UHTREX VHTR (HTGR)
PBR (PBMR)
AVR HTR-10 HTR-PM THTR-300 PMR

Molten-salt
Fluorides

Fuji MSR Liquid-fluoride thorium reactor (LFTR) Molten-Salt Reactor Experiment (MSRE) Integral Molten Salt Reactor (IMSR) TMSR-500

None
(fast-neutron)

Breeder (FBR) Integral (IFR) Liquid-metal-cooled (LMFR) Small sealed transportable autonomous (SSTAR) Traveling-wave (TWR) Energy Multiplier Module (EM2) Reduced-moderation (RMWR) Fast Breeder Test Reactor (FBTR) Dual fluid reactor (DFR)

Generation IV

Sodium (SFR)
BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR CEFR PFR PRISM Lead Helium gas (GFR) Stable Salt Reactor (SSR)

Others

Organic nuclear reactor
Arbus Piqua Aircraft Reactor Experiment

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