Abstract
Several next-generation nuclear reactor designs hold the promise of almost completely solving the worst concerns about nuclear energy. There is still a long way to go, however, before we see the “ultimate reactor” in operation.
IN RECENT YEARS EXPERTS AND NON-EXPERTS ALIKE HAVE looked enthusiastically at nuclear power as a possible solution to the intractable problems posed by climate change and continued fossil-fuel dependence. There are good reasons for such optimism. If the world were to invest only one-half as much as France did during the last half of the twentieth century in nuclear power plant construction, about one-third of global carbon emissions would be eliminated. 1 Of course, aggressive new nuclear development would bring with it some downsides. For instance, a fairly robust worldwide nuclear growth scenario probably would create 1 million more tons of spent nuclear reactor fuel. 2 Finding ways and places to dispose of this waste would not be easy. Some experts believe that a renewed commitment to reprocessing, which removes uranium and plutonium from spent fuel for reuse in power reactors, could do the trick, but reprocessing itself raises significant proliferation issues, among other seemingly insurmountable challenges.
In an attempt to offer my own solution to the shortcomings of the conventional nuclear fuel cycle, I propose using something I have dubbed the “Ultimate Reactor System.” Although it is hypothetical, the Ultimate Reactor System allows us to define exactly what attributes are required to make nuclear energy a sustainable energy source for the planet. The system's requirements would be absolute: no uranium mining, no uranium enrichment, no reprocessing of spent fuel, and no troublesome long-lived nuclear waste products.
The ultimate reactor would have perfect fuel utilization—meaning that any uranium or other heavy metal fuel entering the reactor would ultimately undergo fission—and that demand for new uranium mining would be nil. Fuel for this reactor should be only natural or depleted uranium, possibly thorium, and/or spent nuclear fuel. Outputs would be electricity and/or hydrogen, waste heat, and fission products in need of disposal such as cesium 137 and strontium 90 (these fission products tend to have shorter half lives, hopefully making the waste problem much less politically contentious). 3 There would always be some waste heat, which is required by the laws of thermodynamics, but it would contribute much less to climate change than what is released by burning fossil fuels. 4
Over the years, several proposed designs have attempted to achieve some, if not all, of these benchmarks—most notably, the Integral Fast Reactor, the Molten Salt Reactor, and the newer and less-known Traveling Wave Reactor. The first two systems were mothballed because of high projected development costs and unanswered technical questions. But it should be noted that if they had been further developed, they may have significantly reduced waste generation and reduced proliferation risks. Each of these three proposed systems offers clues and lessons about how such a perfect reactor might be achieved.
To address some of the breeder reactor's shortcomings, U.S. researchers at Idaho National Laboratory began designing the concept of the Integral Fast Reactor in the mid-1980s. The Idaho lab has extensive experience with many of the components needed to build a prototype Integral Fast Reactor, because of years of operating the Experimental Breeder Reactor II. The program developed many innovative and interesting ideas that could be implemented in a future prototype, but it was never well funded. The program was terminated in 1994 by President Bill Clinton when oil prices were low and concerns about climate change were not widespread.
This reactor concept could overcome some proliferation objections by providing technical barriers to diverting highly radioactive “transuranic” material—elements with atomic numbers higher than uranium such as neptunium, americium, curium, plutonium, etc. The recycling of this material is via a reprocessing technology that cannot remove many of the highly radioactive fission products from the fuel. Thus, the reprocessed product is dubbed “self-protecting” as a result of the high-gamma radiation emitted from it. The chemistry involved further cannot produce a plutonium product that is not at least 25 percent contaminated with uranium; the plutonium is always mixed with isotopes that provide substantial decay heat and neutron radioactivity. The process must also be conducted in a heavily shielded, argon gas-filled room, where humans could not enter without rapidly receiving a lethal dose of radiation. All access would be via robot.
The reactor fuel's mixture of radioactive isotopes presents a new unknown to nuclear engineers and safety specialists. Most fuels to date have either been made strictly of uranium or uranium/plutonium mixtures. It is uncertain if the novel fuel in the reactor would have the excellent safety characteristics of conventional nuclear fuel. Moreover, much of the chemistry that would be required for the reactor to work effectively as an ultimate reactor system has not been demonstrated. For instance, a research effort would be needed to keep the reactor's structural and cladding material from becoming contaminated with neptunium, americium, curium, and plutonium; otherwise, another waste stream requiring a geological repository would need to be created. Also, small gaseous and liquid releases to the environment from the chemical processing facilities within the Integral Fast Reactor would be unavoidable—a potential source of public consternation even if there is not much firm science supporting the belief that such releases have negative health impacts.
The molten salt reactor program was finally scrapped by the early 1980s because the technical challenges were considered to be too large and liquid-metal cooled fast breeder reactors showed more economic promise. Although a decision was made to cancel the program, molten salt reactors still have advocates and there are still some small research programs around the world.
… as the fuel fissions and its composition changes during the lifetime of the system, it will not cause the reactor to become unstable, a significant problem in fast reactors.
The design of the more proliferation-resistant Denatured Molten Salt Reactor required continuous fueling with both thorium and low-enriched uranium and required minimal fuel processing (only xenon and krypton gases were removed). No fissile material was recovered. The uranium in the reactor was not weapons usable, due to the continuous addition of uranium 238 and the fact that neither protactinium nor uranium 233 was to be stored outside the reactor. A feed consisting of a mix of thorium and spent commercial fuel could alternatively be burned in the Denatured Molten Salt Reactor, making it a viable candidate for my ultimate reactor.
Molten salt reactors also have the potential to fully recycle conventional light water reactor fuel. Here's how it would work: First, entire spent fuel assemblies from light water reactors, consisting of stainless steel and zirconium-clad uranium oxide fuel interspersed with plutonium, would be lowered into a bath of molten lithium fluoride salt. Then pure fluorine gas would be bubbled through the liquid at high pressure, burning all of the metals (including uranium and plutonium) into fluoride forms that would then be soluble in molten salt. Finally, an electrochemical process would remove fission products and structural remnants such as radioactive iron, nickel, and zirconium for permanent disposal. The remaining liquid salt would be fed into the molten salt reactor as fuel, making reprocessing and fuel fabrication unnecessary. 7
The ability of the reactor design to use thorium-based fuel is also a major benefit and a reason why it still has supporters. The reason is clear—known U.S. thorium reserves are enormous and single-handedly could supply fuel for the world's entire nuclear capacity for the next 2,000 years! A thorium-burning reactor, if engineering practicalities were overcome, could continue to provide replacement nuclear electricity for retiring light water reactors without generating any significant transuranic waste stream of its own. This presumes, however, that at the end of the roughly 60-year service life of the reactor, the molten fuel would be transferred to a new molten salt reactor for continued use. The system has many qualities that would make it a good candidate for an ultimate reactor system.
The Denatured Molten Salt Reactor, designed to deal with some of these proliferation concerns, was hamstrung by its own problems. A complete nuclear accounting of this reactor design shows that the process would be inefficient. The main reason is that the relative proportion of spent fuel in the feedstock must be small, necessitating many more such reactors than traditional fast reactors to burn up the entire existing inventory of spent nuclear fuel. To completely burn the entire accumulated U.S. spent fuel stockpile (which is projected to equal 1 million tons in 50 years) would take a fleet of such reactors a century.
There are some technical obstacles to be overcome as well. The graphite moderator in the core would last only a few years, so the system would regularly have to be shut down completely for core replacement. As such, a viable method of reprocessing and reuse of radioactive graphite would have to be found. Furthermore, some aspects of molten salt chemistry are not well known. For instance, it is suspected that plutonium can precipitate out of molten salt, creating a potential safety issue if too much plutonium were to agglomerate in one location in the reactor's piping and create a hot spot. To further understand phenomena such as these, a long, involved, and costly experimental program would have to be carried out. Such a research program would suffer from the same proliferation concerns as other research involving separated nuclear materials. Lastly, the molten salt itself is of concern because when exposed to radiation inside the core, it produces large quantities of radioactive tritium. Making matters worse, no one has found a way to remove and store kilogram quantities of tritium in a completely safe fashion without leakage to the environment. It seems that another salt (or an entirely different fluid) should be found to address this issue.
The Traveling Wave Reactor has some great features, including no reprocessing, almost no enrichment, and up to 50 percent fuel utilization—a dramatic improvement over existing reactors.
Also the reactor cannot burn spent fuel, unless the fuel is first reprocessed and made into metal. There is also no firm plan for the burning or transmuting of the end-of-life fuel residue in the core, although there are some concepts under discussion. To take the Terrapower system to the point where it functions like an ultimate reactor would require a second generation of Terrapower reactors that would use the first generation's core residue as fuel along with a stream of spent fuel from conventional commercial power reactors.
There are also several technical questions about this design that are familiar ones to the reactor research community. Most important is how the fuel and structural material would be affected after decades or irradiation inside the reactor core. The exposure of materials to radiation is measured by displacements per atom. When a fast moving neutron strikes an atom in a metal it often knocks the atom out of place in the metal's molecular lattice. Roughly speaking, this would be called 1 displacement per atom. As conceived, the Traveling Wave Reactor shall inflict between 400 and 500 such displacements per atom on the materials inside the core by the end of the reactor's lifetime. No one really knows what happens to materials that have undergone such extreme punishment. A liquid sodium-cooled fast reactor that the United States operated for 30 years was irradiated to 200 displacements per atom, and the results were fairly encouraging. Today, there are no U.S. facilities available to obtain more data, however. Terrapower researchers are seeking to use Japanese or Russian facilities for this purpose, but it will take at least four years of full-time testing to accumulate the necessary information. For this reason alone, no one should expect to see a Traveling Wave Reactor operating for at least a decade.
The difficult problems that need to be solved in order to make an ultimate reactor should not be taken to mean that the task is impossible. It is rather to be understood that many years of moderate up-front investment in problem solving will have to be undertaken.
Footnotes
W. C. Sailor, D. Bodansky, C. Braun, S. Fetter, and B. van der Zwaan, “A Nuclear Solution to Global Warming?” Science vol. 288, p.1,177 (2000).
E. Schneider and W. C. Sailor, “Nuclear Fission,” Science and Global Security, vol. 14, fig. 1, p. 191 (2006).
There are also irradiated structural materials (such as cobalt 60) in this stream that have similar hazards to fission products. The U.S. currently stores large quantities of fission products (such as cesium 137) from its weapons production days awaiting disposal. The half-lives of the most dangerous materials are less than or equal to 30 years. A rule of thumb for geological containment is ten half-lives or 300 years.
R.L. Garwin and G. Charpak, Megawatts and Megatons, A Turning Point in the Nuclear Age (Alfred A. Knopf: New York, 2001) p. 242.
U. Gat and J. R. Engel, “Non-Proliferation Attributes of Molten Salt Reactors,” Nuclear Engineering and Design, vol. 201, pp. 327–334 (2000).
J. R. Engel et al., Conceptual Design Characteristics of a Denatured Molten-Salt Reactor with Once-Through Fueling (Oak Ridge National Laboratory: Oak Ridge, Tennessee, July 1980).
This example is an extrapolation from research currently being pursued by Hitachi. See, Y. Kani et al., “New Reprocessing System for Spent Nuclear Reactor Fuel Using Fluoride Volatility Method,” Journal of Fluorine Chemistry, vol. 130, no. 1, pp. 74–82 (2009).
S. M. Feinberg, “Discussion Comment,” (Rec. Proc. Session B-10, International Conference on the Peaceful Uses of Energy, United Nations, Geneva, 1958); E. Teller, M. Ishikawa, and L. Wood, “Completely Automated Nuclear Power Reactors for Long Term Operation,” (Proceedings of the Frontiers in Physics Symposium, American Physical Society and the American Association of Physics Teachers Meeting, Lubbock, Texas, 1995).
“John Gilleland: On the Traveling-Wave Reactor,” Nuclear News, September 2009, pp. 30–32.
K. D. Weaver et al., “Extending the Nuclear Fuel Cycle with Traveling-Wave Reactors,” (Proceedings of Global 2009 Conference, Paris, September 6–11, 2009).
