Nuclear fusion-fission hybrid
Hybrid nuclear fusion-fission (hybrid nuclear power) is a proposed means of generating power by use of a combination of nuclear fusion and fission processes. The basic idea is to use high-energy fast neutrons from a fusion reactor to trigger fission in otherwise nonfissile fuels like U-238 or Th-232. Each neutron can trigger several fission events, multiplying the energy released by each fusion reaction hundreds of times. This would not only make fusion designs more economical in power terms, but also be able to burn fuels that were not suitable for use in conventional fission plants, even their nuclear waste.
The concept dates to the 1950s, and was strongly advocated by Hans Bethe during the 1970s. At that time the first powerful fusion reactors were being built, but it would still be many years before they could be economically competitive. Hybrids were proposed as a way of greatly accelerating their market introduction, producing energy even before the fusion systems reached break-even. However, detailed studies of the economics of the systems suggested they could not compete with existing fission reactors. The idea was abandoned and lay dormant until the 2000s, when the continued delays in reaching break-even led to a brief revival around 2009, notably as the basis of the LIFE program. The concept has since become dormant again.
Conventional fission power plants rely on the chain reaction caused when nuclear fission events release neutrons that cause further fission events. Each fission event in uranium releases two or three neutrons, so by careful arrangement and the use of various absorber materials, you can balance the system so one of those neutrons causes another fission event while the other one or two are lost. This careful balance is known as criticality.
Natural uranium is a mix of several isotopes, mainly a trace amount of U-235 and over 99% U-238. When they undergo fission, both of these elements release neutrons with energies around 1 to 2 MeV. This energy is too low to cause fission in U-238, which means it cannot sustain a chain reaction. U-235 will undergo fission when struck by neutrons of this energy, but does so much easier when the neutrons have much less energy, the so-called thermal neutrons. To provide this, neutron moderator materials are used to slow the neutrons, giving off heat that is extracted for power. Common moderators like water often absorb some of the neutrons, reducing the number available for fission to a point too low to keep the chain reaction going. To keep criticality, most reactor designs concentrate, or enrich, the fuel, increasing the amount of U-235 to produce enriched uranium, while the leftover, now mostly U-238, is a waste product known as depleted uranium.
A fission reactor burns off its supply of U-235 over a short period, on the order of a few months. A combination of burnup of the U235 along with the creation of neutron absorbers, or poisons, as part of the fission process eventually results in the fuel mass not being able to maintain criticality. This burned up fuel has to be removed and replaced with fresh fuel. The result is nuclear waste that is highly radioactive and filled with long lived radionuclides that present a safety concern.
The waste contains most of the U-235 it started with, only 1% or so of the energy in the fuel is extracted by the time it reaches the point were it is no longer fissile. One solution to this problem is to reprocess the fuel, which uses chemical processes to separate the U-235 (and other non-poison elements) from the waste, and then uses that U-235 in fresh fuel loads. This reduces the amount of new fuel that needs to be mined, and also concentrates the unwanted portions of the waste into a smaller load. Reprocessing is expensive, however, and has generally been more expensive than simply buying fresh fuel from the mine.
Another possibility is tobreed Pu-239 from the U-238 through neutron capture, or various other other means. In order to do this, higher energy neutrons are required, which means they cannot be moderated as in a conventional reactor. The simplest way to achieve this is to further enrich the original fuel well beyond what is needed for use in a moderated reactor, to the point where the U-235 maintains criticality even with the fast neutrons. The extra fast neutrons escaping the fuel load can then be used to breed fuel in a U-238 assembly surrounding the reactor core, most commonly taken from the stocks of depleted uranium. The Pu-239 is then chemically separated and mixed into fresh fuel for conventional reactors, in the same fashion as normal reprocessing, but the total volume of fuel created in this process is much greater. In spite of this, like reprocessing, the economics of breeder reactors has proven unattractive, and commercial breeder plants have ceased operation.
Fusion reactors typically burn a mixture of deuterium (D) and tritium (T). When heated to millions of degrees, the kinetic energy in the fuel begins to overcome the natural electrostatic repulsion between nuclei, the so-called coulomb barrier, and the fuel begins to undergo fusion. This reaction gives off an alpha particle and a high energy neutron of 14 MeV. A key requirement to the economic operation of a fusion reactor is that the alphas deposit their energy back into the fuel mix, heating it so that additional fusion reactions take place. This leads to a condition not unlike the chain reaction in the fission case, known as ignition.
Deuterium can be obtained by the separation of hydrogen isotopes in sea water (see heavy water production). Tritium has a short half life of just over a decade, so only trace amounts are found in nature. To fuel the reactor, the neutrons from the reaction are used to breed more tritium through a reaction in a blanket of lithium surrounding the reaction chamber. Tritium breeding is key to the success of a fusion cycle, and to date this technique has not been demonstrated. Predictions based on computer modelling suggests that the breeding ratios are quite small and a fusion plant would barely be able to cover its own use. Many years would be needed to breed enough surplus to start another reactor.
Fusion-fission designs essentially replace the lithium blanket with a blanket of fission fuel, either natural uranium ore or even nuclear waste. The fusion neutrons have more than enough energy to cause fission in the U-238, as well as many of the other elements in the fuel, including some of the transuranic waste elements. The reaction can continue even when all of the U-235 is burned off; the rate is controlled not by the neutrons from the fission events, but the neutrons being supplied by the fusion reactor.
Fission occurs naturally because each event gives off more than one neutron capable of producing additional fission events. Fusion, at least in D-T fuel, gives off only a single neutron, and that neutron is not capable of producing more fusion events. When that neutron strikes fissile material in the blanket, one of two reactions may occur. In many cases, the kinetic energy of the neutron will cause one or two neutrons to be struck out of the nucleus without causing fission. These neutrons still have enough energy to cause other fission events. In other cases the neutron will be captured and cause fission, which will release two or three neutrons. This means that every fusion neutron in the fusion-fission design can result in anywhere between two and four neutrons in the fission fuel.
This is a key concept in the hybrid concept, known as fission multiplication. For every fusion event, several fission events may occur, each of which gives off much more energy than the original fusion, about 11 times. This greatly increases the total power output of the reactor. This has been suggested as a way to produce practical fusion reactors in spite of the fact that no fusion reactor has yet reached break-even, by multiplying the power output using cheap fuel or waste. However, a number of studies have repeatedly demonstrated that this only becomes practical when the overall reactor is very large, 2 to 3 GWt, which makes it expensive to build.
These processes also have the side-effect of breeding Pu-239 or U-233, which can be removed and used as fuel in conventional fission reactors. This leads to an alternate design where the primary purpose of the fusion-fission reactor is to reprocess waste into new fuel. Although far less economical than chemical reprocessing, this process also burns off some of the nastier elements instead of simply physically separating them out. This also has advantages for non-proliferation, as enrichment and reprocessing technologies are also associated with nuclear weapons production. However, the cost of the nuclear fuel produced is very high, and is unlikely to be able to compete with conventional sources.
A key issue for the fusion-fission concept is the number and lifetime of the neutrons in the various processes, the so-called neutron economy.
In a pure fusion design, the neutrons are used for breeding tritium in a lithium blanket. Natural lithium consists of about 92% Li-7 and the rest is mostly Li-6. Li-7 requires neutron energies even higher than those released by fission, around 5 MeV, well within the range of energies provided by fusion. This reaction produces T, Helium-3, and another slow neutron. Li-6 can react with high or low energy neutrons, including those released by the Li-7 reaction. This means that a single fusion reaction can produce several tritiums, which is a requirement if the reactor is going to make up for natural decay and losses in the fusion processes.
When the lithium blanket is replaced, or supplanted, by fission fuel in the hybrid design, neutrons that do react with the fissile material are no longer available for tritium breeding. The new neutrons released from the fission reactions can be used for this purpose, but only in Li-6. One could process the lithium to increase the amount of Li-6 in the blanket, making up for these losses, but the downside to this process is that the Li-6 reaction only produces one tritium atom. Only the high-energy reaction between the fusion neutron and Li-7 can create more than one tritium, and this is essential for keeping the reactor running.
To address this issue, at least some of the fission neutrons must also be used for tritium breeding in Li-6. Every one that does is no longer available for fission, reducing the reactor output. This requires a very careful balance if one wants the reactor to be able to produce enough tritium to keep itself running, while also producing enough fission events to keep the fission side energy positive. If these cannot be accomplished simultaneously, there is no reason to build a hybrid. Even if this balance can be maintained, it might only occur at a level that is economically infeasible.
Through the early development of the hybrid concept the question of overall economics appeared difficult to handle. A series of studies starting in the late 1979s provided a much clearer picture of the hybrid in a complete fuel cycle, and allowed the economics to be better understood. These studies appeared to indicate there was no reason to build a hybrid.
One of the most detailed of these studies was published in 1980 by Los Alamos National Laboratory (LANL). Their study noted that the hybrid would produce most of its energy indirectly, both though the fission events in its own reactor, and much more by providing Pu-239 to fuel conventional fission reactors. In this overall picture, the hybrid is essentially identical to the breeder reactor, which uses fast neutrons from plutonium fission to breed more fuel in a fission blanket in largely the same fashion as the hybrid. Both require chemical processing to remove the bred Pu-239, both presented the same proliferation and safety risks as a result, and both produced about the same amount of fuel. Since that fuel is the primary source of energy in the overall cycle, the two systems were almost identical in the end.
What was not identical, however, was the technical maturity of the two designs. The hybrid would require considerable additional research and development before it would be known if it could even work, and even if that were demonstrated, the end result would be an system essentially identical to breeders which were already being built at that time. The report concluded:
The investment of time and money required to commercialize the hybrid cycle could only be justified by a real or perceived advantage of the hybrid over the classical FBR. Our analysis leads us to conclude that no such advantage exists. Therefore, there is not sufficient incentive to demonstrate and commercialize the fusion-fission hybrid.
The fusion process alone currently does not achieve sufficient gain (power output over power input) to be viable as a power source. By using the excess neutrons from the fusion reaction to in turn cause a high-yield fission reaction (close to 100%) in the surrounding subcritical fissionable blanket, the net yield from the hybrid fusion-fission process can provide a targeted gain of 100 to 300 times the input energy (an increase by a factor of three or four over fusion alone). Even allowing for high inefficiencies on the input side (i.e. low laser efficiency in ICF and Bremsstrahlung losses in Tokamak designs), this can still yield sufficient heat output for economical electric power generation. This can be seen as a shortcut to viable fusion power until more efficient pure fusion technologies can be developed, or as an end in itself to generate power, and also consume existing stockpiles of nuclear fissionables and waste products.
In the LIFE project at the Lawrence Livermore National Laboratory LLNL, using technology developed at the National Ignition Facility, the goal is to use fuel pellets of deuterium and tritium surrounded by a fissionable blanket to produce energy sufficiently greater than the input (laser) energy for electrical power generation. The principle involved is to induce inertial confinement fusion (ICF) in the fuel pellet which acts as a highly concentrated point source of neutrons which in turn converts and fissions the outer fissionable blanket. In parallel with the ICF approach, the University of Texas at Austin is developing a system based on the tokamak fusion reactor, optimising for nuclear waste disposal versus power generation. The principles behind using either ICF or tokamak reactors as a neutron source are essentially the same (the primary difference being that ICF is essentially a point-source of neutrons while Tokamaks are more diffuse toroidal sources).
Use to dispose of nuclear waste
The surrounding blanket can be a fissile material (enriched uranium or plutonium) or a fertile material (capable of conversion to a fissionable material by neutron bombardment) such as thorium, depleted uranium or spent nuclear fuel. Such subcritical reactors (which also include particle accelerator-driven neutron spallation systems) offer the only currently-known means of active disposal (versus storage) of spent nuclear fuel without reprocessing. Fission by-products produced by the operation of commercial light water nuclear reactors (LWRs) are long-lived and highly radioactive, but they can be consumed using the excess neutrons in the fusion reaction along with the fissionable components in the blanket, essentially destroying them by nuclear transmutation and producing a waste product which is far safer and less of a risk for nuclear proliferation. The waste would contain significantly reduced concentrations of long-lived, weapons-usable actinides per gigawatt-year of electric energy produced compared to the waste from a LWR. In addition, there would be about 20 times less waste per unit of electricity produced. This offers the potential to efficiently use the very large stockpiles of enriched fissile materials, depleted uranium, and spent nuclear fuel.
In contrast to current commercial fission reactors, hybrid reactors potentially demonstrate what is considered inherently safe behavior because they remain deeply subcritical under all conditions and decay heat removal is possible via passive mechanisms. The fission is driven by neutrons provided by fusion ignition events, and is consequently not self-sustaining. If the fusion process is deliberately shut off or the process is disrupted by a mechanical failure, the fission damps out and stops nearly instantly. This is in contrast to the forced damping in a conventional reactor by means of control rods which absorb neutrons to reduce the neutron flux below the critical, self-sustaining, level. The inherent danger of a conventional fission reactor is any situation leading to a positive feedback, runaway, chain reaction such as occurred during the Chernobyl disaster. In a hybrid configuration the fission and fusion reactions are decoupled, i.e. while the fusion neutron output drives the fission, the fission output has no effect whatsoever on the fusion reaction, completely eliminating any chance of a positive feedback loop.
There are three main components to the hybrid fusion fuel cycle: deuterium, tritium, and fissionable elements. Deuterium can be derived by separation of hydrogen isotopes in sea water (see heavy water production). Tritium may be generated in the hybrid process itself by absorption of neutrons in lithium bearing compounds. This would entail an additional lithium bearing blanket and a means of collection. The third component is externally derived fissionable materials from demilitarized supplies of fissionables, or commercial nuclear fuel and waste streams. Fusion driven fission also offers the possibility of using Thorium as a fuel, which would greatly increase the potential amount of fissionables available. The extremely energetic nature of the fast neutrons emitted during the fusion events (up to 0.17 the speed of light) can allow normally non-fissioning U-238 to undergo fission directly (without conversion first to Pu-239), enabling refined natural Uranium to be used with very low enrichment, while still maintaining a deeply subcritical regime.
Practical engineering designs must first take into account safety as the primary goal. All designs should incorporate passive cooling in combination with refractory materials to prevent melting and reconfiguration of fissionables into geometries capable of un-intentional criticality. Blanket layers of Lithium bearing compounds will generally be included as part of the design to generate Tritium to allow the system to be self-supporting for one of the key fuel element components. Tritium, because of its relatively short half-life and extremely high radioactivity, is best generated on site to obviate the necessity of transportation from a remote location. D-T fuel can be manufactured on site using Deuterium derived from heavy water production and Tritium generated in the hybrid reactor itself. Nuclear spallation to generate additional neutrons can be used to enhance the fission output, with the caveat that this is a tradeoff between the number of neutrons (typically 20-30 neutrons per spallation event) against a reduction of the individual energy of each neutron. This is a consideration if the reactor is to use natural Thorium as a fuel. While high energy (0.17c) neutrons produced from fusion events are capable of directly causing fission in both Thorium and U-238, the lower energy neutrons produced by spallation generally cannot. This is a tradeoff which affects the mixture of fuels against the degree of spallation used in the design.
- Subcritical reactor, a broad category of designs using various external neutron sources including spallation to generate non-self-sustaining fission (Hybrid Fusion-Fission Reactors fall into this category).
- Muon-catalyzed fusion, which uses exotic particles to achieve fusion ignition at relatively low temperatures.
- Breeder reactor, a nuclear reactor that generates more fissile material in fuel than it consumes.
- Generation IV reactor, next generation fission reactor designs claiming much higher safety, and greatly increased fuel use efficiency.
- Traveling wave reactor, a pure fission reactor with a moving reaction zone, which is also capable of consuming wastes from LWRs and using depleted Uranium as a fuel.
- Liquid fluoride thorium reactor, a fission reactor which uses molten thorium fluoride salt fuel, capable of consuming wastes from LWRs.
- Integral Fast Reactor, a fission fast breeder reactor which uses reprocessing via electrorefining at the reactor site, capable of consuming wastes from LWRs and using depleted Uranium as a fuel.
- Aneutronic fusion a category of nuclear reactions in which only a small part (or none) of the energy released is carried away by energetic neutrons.
- Project PACER, a reverse of this concept, attempts to use small fission explosions to ignite hydrogen fusion (fusion bombs) for power generation
- Cold fusion
- Gerstner, E. (2009). "Nuclear energy: The hybrid returns" (PDF). Nature 460 (7251): 25–8. doi:10.1038/460025a. PMID 19571861.
- Brennen 2005, p. 16.
- Brennen 2005, p. 19.
- Bethe 1979, p. 48.
- Tenney, F. et al. (November 1978). A Systems Study of Tokamak Fusion-Fission Reactors (PDF) (Technical report). Princeton Plasma Physics Laboratory. pp. 336–337.
- Barrett & Hardie 1980.
- Barrett & Hardie 1980, p. 2.
- Barrett & Hardie 1980, p. 3.
- Bethe 1979.
- Barrett, R.J.; Hardie, R.W. (September 1980). The Fusion-Fission Hybrid As an Alternative to the Fast Breeder Reactor (PDF) (Technical report). Los Alamos Scientific Laboratory.
- Bethe, Hans (May 1979). "The Fusion Hybrid" (PDF). Physics Today: 44–51. ISSN 0031-9228.
- Brennen, Christopher (2005). An Introduction to Nuclear Power Generation (PDF). Dankat Publishing.
- A.P. Barzilov, A.V. Gulevich, O.F. Kukharchuk and A.V. Zrodnikov,. "Hybrid Fission-Fusion Reactor Initiated by a Laser". Obninsk, Russia: Institute of Physics & Power Engineering,.
- MIT. "Fusion-Fission Research Workshop: includes workshops final report, related white papers and publications.".
- Potential Role of Lasers for Sustainable Fission Energy Production and Transmutation of Nuclear Waste C.D. Bowman and J. Magill
- Laser Inertial Fusion-Fission Energy (LIFE) Project at the Lawrence Livermore National Laboratory,
- Nuclear Fusion-Fission Hybrid Could Destroy Nuclear Waste And Contribute to Carbon-Free Energy Future University of Texas at Austin
- Ralph Moir's fusion-fission hybrid page - contains many research papers about the topic
- International Thorium Energy Organisation - www.IThEO.org