INSTITUTE FOR ENERGY ANDENVIRONMENTAL RESEARCH

Traveling Wave Reactors:
Sodium-cooled Gold at
the End of a Nuclear Rainbow?
By Arjun Makhijani, Ph.D.
September 2013

Traveling Wave Reactors:

Sodium-cooled Gold at the End of a Nuclear Rainbow?
By Arjun Makhijani, Ph.D.
The “Traveling Wave Reactor” (TWR) is a proposed reactor design that belongs toa set known as Generation IV designs that are different in a number of respects thanthe current commercial designs which use water to cool the reactor and slow down(“moderate”) the neutrons that sustain the chain reaction. It was first conceived in
1958 but has been intensively investigated only since about 2006, most notably by
TerraPower, a company formed in 2008 by venture capitalists, including Bill Gates ofMicrosoft fame (TerraPower 2013a and Intellectual Ventures 2013).
The TWR is a sodium-cooled “fast” reactor design, which means that energetic(“fast”) neutrons sustain the chain reaction. The heat created by fission is carriedaway by liquid sodium, which is used to boil water (in a two-step process); in turn, thesteam is used to drive a turbine-generator set to generate electricity. A TWR has neverbeen built. However, the TWR has much in common with other sodium-cooled fast
reactors though there are some important differences. Since many sodium-cooled fast
reactors have been built over more than six decades in several countries, it is worth
examining that experience to help evaluate the prospects for the TWR.

Sodium-cooled reactor experience
Sodium-cooled fast reactors have a checkered history. Some have operated well,while others have done poorly. The most recent commercial demonstration reactors
belong in the latter category. The French demonstration reactor, Superphénix, operated at an average capacity factor of less than 7 percent over 11 years before being
shut in 1996; the formal decision not to reopen it was made in 1998 (IPFM 2010, p. 10
and Chapter 2). The Japanese Monju reactor, commissioned in 1994, and connectedto the grid in 1995, had a sodium leak and fire in 1995. It was closed until May 2010,
when it was restarted for testing, but suffered another accident in August 2010. (NYT2011). It has not been restarted since. A schematic of pool-type and loop-type sodiumcooled reactors is shown in Figure 1 (see next page).

Sodium-cooled fast reactors have a checkered history. Some have operated well, whileothers have done poorly. The most recent commercial demonstration reactors belong
in the latter category.
1

2

Figure 1: Schematic of Pool-Type and Loop-Type Sodium-Cooled Reactors. Turbine and electric generator not shown. (Source: Wikimedia
Commons, author: Graevemoore, at http://commons.wikimedia.org/wiki/File:LMFBR_schematics2.svg)

FIGURE 1

Institute for Energy and Environmental Research (IEER)One of the most difficult engineering problems with sodium-cooled reactors has to
do with the fact that sodium burns on contact with air and explodes on contact withwater. Further, some of the non-radioactive sodium nuclei of the coolant absorb aneutron and are thereby converted to intensely radioactive sodium-24. Leaks create
difficult clean-up and maintenance and repair problems. This is especially so forprimary leaks, but also true for secondary loop sodium leaks where no radioactivity
releases are involved – as was the case with the 1995 Monju fire. Leaks are often
followed by weeks, months, or even years of repair, cleanup, testing and inspection
before the reactor can be restarted. Further, leaks have been a common problem insodium-cooled breeder programs, including in France, the UK, India, Russia, andJapan (IPFM 2010, various chapters). Core meltdown accidents can also occur: twoof the U.S. sodium-cooled breeders have had partial core meltdowns (IPFM 2010,
pp. 92, 95). Sodium-cooled reactors have some safety advantages relative to presentday light water reactors, such as operation at low pressure, in contrast to light water
reactors. But they also have safety disadvantages, including the potential for thereactor to continue to sustain a chain reaction in the event of coolant loss (IPFM
2010, pp. 8-9).
Even apart from the poor reliability in many cases, sodium-cooled breeder reactor
capital costs have been very variable and have not decreased over time. Fermi I,
built in the 1960s, cost about $4,000 per kilowatt, while the Fast Flux Test Facility,
operational in 1980, cost over $10,000 per kilowatt. Superphénix cost, commissioned
in 1986, about $4,800 per kilowatt, but Monju, commissioned nearly a decade later,
cost over $20,000 per kilowatt (all in 1996 dollars – Makhijani 2010, Table 3). Overall, it is expected that costs of sodium-cooled breeders will be significantly higher
than current reactors (IPFM 2010, p. 7), despite the fact that about $100 billion havebeen spent worldwide (2007 dollars) on the attempt to commercialize sodium-cooled
breeder reactors, so far without success (Makhijani 2010, p. 36, where additionalreferences can be found).
The ups and downs of the successes and failures of sodium-cooled reactors, including
the commercial failure of the most recent ones, indicate that there has been no demonstrable learning curve. Proponents of sodium-cooled reactors, including travelingwave reactors, tend not to focus on how they plan to overcome the problematic partsof the sodium-cooled design history, centered in large part on sodium-related problems, but rather tend to focus on the vast available raw material to produce a large
amount of power for the indefinite future.

Overall, it is expected that costs of sodium-cooled breeders will be significantly higher
than current reactors, despite the fact that about $100 billion have been spent worldwide (2007 dollars) on the attempt to commercialize sodium-cooled breeder reactors,
so far without success.
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Traveling Wave Reactors: Sodium-cooled Gold at the End of a Nuclear Rainbow?

This misplaced emphasis on the theoretical ability of breeder reactors to stretch theuranium resource greatly has historically led to messianic pronouncements and promises. Compare, for instance, the statement in Ellis et al. 2010 about TWRs: “Such highfuel efficiency, combined with an ability to use uranium recovered from river water or
sea-water (which has been recently demonstrated to be technically and economicallyfeasible) suggests that enough fuel is readily available for TWRs to generate electricity for 10 billion people at United States per capita levels for million-year time-scales”
with Alvin Weinberg, perhaps the best known Oak Ridge National Laboratory scientist,
recalling, in 1981, his attitude in the 1950s: “…you had in the uranium in the rocks, inprinciple, an inexhaustible energy source–enough to keep you going for hundreds ofmillions of years. I got very, very excited about that, because here was an embodimentof a way to save mankind. I guess I acquired a little bit of the same spirit as the Ayatollah[Khomeini] has at the moment” (as quoted in Ford 1982, p. 25). Other examples can befound in Ford 1982 and in Makhijani and Saleska 1999, Chapter 3.
The TWR would use metal fuel, with a liquid sodium thermal bond (Ellis et al. 2010).
This liquid sodium inside the fuel rod is meant to provide a good thermal connection
with the sodium coolant and is similar to the fuel used in past sodium-cooled reactors.
Such spent fuel would be unsuitable for disposal in a repository. The sodium has tobe removed before disposal, a costly task, given that spent fuel is highly radioactive
and sodium is pyrophoric.

Traveling Wave Reactor Specifics
The TWR is different in some specific respects from other sodium-cooled breeders.
The most important difference is that in the TWR the breeding would be done in thecore; by design the newly created plutonium would be burned without having to be
separated first. In a conventional breeder, the plutonium breeding is done in a “blanket” outside the core; the plutonium would then be separated and fabricated into fuelin a reprocessing plant (onsite or offsite).
The initial TWR design proposed was that of a reactor in which the chain reaction front
would proceed like a slow wave across the core much like a cigarette burning from tip
to butt, with the ashes remaining (inside, in the case of the reactor) as waste. TerraPower
has a video illustration of this concept; it can be seen on a YouTube video simulation(TerraPower 2013c). There would be little or no unused fissile or fertile material. An
essentially 100 percent use of the uranium resource was implied. More detailed design
work has apparently led to a change in this conceptual design in favor of a core that ismore like a traditional sodium-cooled breeder, except that the fuel would be “shuffled”
periodically, enable better breed of fuel in the core and long periods between refueling(Ellis et al. 2010, and Garwin 2010). Contrary to early implications, illustrated in the
TerraPower video mentioned above, the first generation of the TWR would achieve aburnup of just 15 percent (Ellis et al. 2010).1
1 Design details of the present (2013) configuration are not publicly available.

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Further, the design cannot burn the plutonium and uranium in present-day spent fuelinventory from today’s light water reactors without reprocessing – a costly enterprisethat would increase proliferation risks. Figure 2 (see next page) shows a diagram ofthe latest TWR public design.
Reprocessing (called “repurposing” by proponents – Ellis et al. 2010) spent fuel could
substantially increase the fraction of the uranium resource that is used upward from 15
percent to over 50 percent, but at the cost of increased proliferation risk. Proponents
claim that “repurposing” the fuel can be done “without the proliferation risk of fissile
material separations” (Ellis et al. 2010). This claim does not stand scrutiny. Ellis et al.
propose the same process as the one being developed for Experimental Fast Breeder
II fuel. Figure 3 (see page 7) shows a pilot electrorefiner, at the Idaho National Laboratory, where the first sodium-cooled reactor, called Experimental Breeder Reactor
I, was built in 1951. This technology, also known as “pyroprocessing” and “electrometallurgical processing,” was developed for dealing with sodium-bonded metal fuelused in sodium-cooled breeder reactors (Benedict et al. 2007). A 2009 study by U.S.
national laboratory experts concluded that the various reprocessing technologies, including the electrorefining process discussed in Ellis et al. 2010, would provide little
additional proliferation resistance, so far as proliferant states were concerned, compared to the present-day PUREX process that has been a source of great concern (Bariet al. 2009). It is not a matter of what present-day nuclear weapon states would dowith the technology, but what potential proliferant states could do with it.
Even with very high use of the uranium resource and repeated reprocessing, a deep
geologic repository would be needed in any case. This is a central reason that theBlue Ribbon Commission on America’s Nuclear Future recommended that a repository program should proceed independent of the nuclear power and reprocessing pathchosen by the United States (BRC 2012, p. 27).
A once-through open cycle TWR would have an advantage over conventional breeders in that no reprocessing would be needed to achieve much greater use of the uranium resource relative to today’s light water reactors. Direct disposal of spent fuelwould reduce proliferation risk relative to conventional breeders, but this it would
pose considerable difficulties. Specifically, the sodium used as a thermal bond in thefuel would have to be removed first. Present-day reactor spent fuel requires no comparable step and can be put into disposal containers without such intermediate steps,
risks, and costs.
By the same token, the disposal of TWR spent fuel would create its own problems.
The spent fuel would contain residual uranium and unburned transuranic radionuclides including plutonium-239. It would also contain the usual variety of short- andlong-lived fission products, except that a much larger amount would be contained perunit volume due to the much higher burnup.
5Traveling Wave Reactors: Sodium-cooled Gold at the End of a Nuclear Rainbow?

FIGURE 2

Figure 2: Traveling wave reactor. The core is at the bottom center. (Source: TerraPower.
TWR-P Reactor, at http://terrapower.com/uploads/multimedia/TWR-P.jpg)

6Institute for Energy and Environmental Research (IEER)FIGURE 3

Figure 3: Pilot “Electrorefiner” for Experimental Breeder Reactor II at Idaho National
Laboratory. Reprocessing for the TWR would presumably use a similar reprocessing technology. (Source: Wikimedia Commons, author: Argonne National Laboratory, at http://commons.wikimedia.org/wiki/File:EBRElectrorefiner.jpg)

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Traveling Wave Reactors: Sodium-cooled Gold at the End of a Nuclear Rainbow?

As a consequence, the local thermal loads created by TWR spent fuel in a repository
would be much higher than with today’s spent
fuel. This may make the site selection and reposiThe TWR would use uranium
tory design more difficult than it already is. For infuel enriched to a much higher
stance, it may increase the risk of local fissures inthe vicinity of the disposal locations; such fissuresdegree than present light
could open up more pathways for radioactive materials to reach the human environment relative towater reactors — 15 percent,present-day spent fuel. We have not come acrossinstead of 4 to 5 percent. It isany serious analysis of waste disposal and repository issues from proponents of TWRs that woulda relatively short step from 15
be created by direct disposal of very high burnup
percent enriched uranium to
TWR spent fuel.

90 percent enriched weapons

The TWR would use uranium fuel enriched to amuch higher degree than present light water reacgrade uranium.
tors — 15 percent, instead of 4 to 5 percent. It
is a relatively short step from 15 percent enriched uranium to 90 percent enrichedweapons grade uranium.
One extravagant claim is that the TWR would only need “one uranium enrichment
plant per planet” (Wald 2009), the reality would likely be quite different. Without reprocessing, each first generation TWR would require about 1 metric ton of 15 percent
enriched uranium per year (Garwin 2010).2 While this reduces the separative workrequired by about a factor of five relative to light water reactors, widespread adoptionof TWRs could require large numbers of enrichment plants configured to produce uranium enriched to a degree that is much closer to weapons grade than present-day reactors. If reconfigured, an enrichment plant that produces 1 ton of 15 percent enricheduranium would produce about 146 kg of 90 percent HEU, or nearly 6 bombs worth.
At a typical size of 3 million kilograms of separative work per year, a single enrichment
plant would fuel about 90 TWRs. In bomb-enrichment configuration, each such plant
could produce well over 500 bombs worth of enriched uranium. Proponents have suggested that the world could adopt this as its main power source to provide electricity at
the current U.S. level worldwide for a global population of 10 billion (Ellis et al. 2010).

If reconfigured, an enrichment plant that produces 1 ton of 15 percent enricheduranium would produce about 146 kg of 90 percent HEU, or nearly 6 bombs worth.
2
Garwin calculates that 60 metric tons of 15% enriched fuel would be needed for reactor operation
at a level of 3 gigawatts thermal for 60 years (in addition to 320 metric tons of depleted uranium).

8Institute for Energy and Environmental Research (IEER)

Assuming TWRs would supply 70 percent of this total, a highly unrealistic 10,000
reactors of 1,000 megawatts (one gigawatt) each would have to be built. Even if
burnup is doubled without reprocessing through fuel element repositioning in advanced TWRs, about 50 typical enrichment plants
would be needed to fuel them. The replacement of old
Safeguarding this global
units (at a life of 50 years) would require one new enenrichment capacity
richment plant to come on line each year. Recall thatone similar plant enriching uranium to 20 percent
sufficiently to ensure that justin Iran has created a major and prolonged security crinot a single bomb’s worth sis that is so far unresolved. Fifty plants would becapable of producing well over 25,000 bombs worth
was diverted would beof highly enriched uranium each year. Safeguarding
this global enrichment capacity sufficiently to ensure
a very tough, possiblythat not a single bomb’s worth was diverted would be
insuperable job.
a very tough, possibly insuperable, job. Less unrealistically, one might consider the International Atomic
Energy Agency’s high nuclear estimate of 1,137 gigawatts for the year 2050 (IAEA
2012, p. 17) and imagine that TWRs would supply 1,000 gigawatts of this total.
Assuming these to be first generation TWRs since they would be built before 2050,
even this smaller number would require ten typical operating enrichment plants,
with one new plant being required about every five years as a replacement.
It is highly unlikely that enrichment plants can be internationalized or centralized in
the West, a necessary precondition for a few very large plants to supply the enricheduranium for TWRs, should they become the mainstays of world electricity supply.
Several decades of such proposals have not yielded a single enrichment or reprocessing facility under international control. Article IV of the Nuclear Non-Proliferation
Treaty (NPT) has guaranteed to members an “inalienable right” to commercial nuclear technology that signatory governments are loath to give up. It should be noted that
reprocessing has not been ruled out for TWRs and indeed is explicitly mentioned as
one option for stretching the uranium resource further (Ellis et al. 2010). Reprocessing could reduce enrichment requirements significantly on the front end, but it would
increase proliferation risks at the back end, where the separated material can be refined into weapons-usable plutonium (Bari et al. 2009).
In sum, contrary to claims, these heuristic calculations show that TWRs, like othersodium-cooled breeders, would create significant proliferation risks, with or without
reprocessing, were they to be used as a mainstay of global power generation.

Contrary to claims, these heuristic calculations show that TWRs, like othersodium-cooled breeders, would create significant proliferation risks, with or without
reprocessing, were they to be used as a mainstay of global power generation.
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Traveling Wave Reactors: Sodium-cooled Gold at the End of a Nuclear Rainbow?

Resource and Cost Considerations
The main argument that has been made for TWRs is that they can greatly expand theuse of the uranium resource without reprocessing. But a paucity of uranium resources
is not holding back nuclear power – it is the capital cost of the reactors. Reducing
the cost of uranium resources significantly will do almost nothing to alleviate thisproblem, since the cost of mined uranium in existing power plants is roughly two percent of the overall cost of nuclear power. The much lower cost of mined uranium for
TWRs will at most eliminate a few percent of the cost of power (including all capitaland operating costs).3
The high capital cost and financial risk of nuclear reactors led the CEO of General
Electric to say that he would “never do nuclear” were he a utility CEO because hewould have to “bet my company” on the project (Financial Times 2007). TWRs do
nothing to solve this problem; on the contrary, being sodium-cooled breeders, they
are likely to be more expensive than existing reactors. Even if TWR capital costs are
just $1,000 per kilowatt more than light water reactors, the added capital cost per
kWh will be about one cent per kWh, which is roughly five times the cost of mineduranium for LWRs.4
So far as the ability of TWRs to contribute to a low-carbon source of electricity,
it should be noted that the target date for elimination of most fossil fuel use (80 to
95 percent) for climate protection is 2050, about the same year that Japan hopes tocommercialize the conventional sodium-cooled breeder (IPFM 2010, p. 53). On the
more optimistic side, French breeder reactor advocates aim to replace half of France’s
nuclear capacity with sodium-cooled breeders by 2050, with the other half being lightwater reactors (World Nuclear Association 2013).

The main argument that has been made for TWRs is that they can greatly expand
the use of the uranium resource without reprocessing. But a paucity of uranium
resources is not holding back nuclear power – it is the capital cost of the reactors.
Reducing the cost of uranium resources significantly will do almost nothing toalleviate this problem.
3
At $100 per kilogram of natural uranium. Nuclear electricity cost is taken as about 9 cents/ kWh,based on the AP1000 reactors under construction in Georgia and 8 percent average cost of capital. Elliset al. 2010 estimate the uranium cost at 5 percent by assuming a very low cost of nuclear power at 5
cents/kWh.
4 TerraPower’s CEO, John Gilleland, expects the TWR to cost about the same as today’s reactors but
has been quoted as saying that “the jury is still not in on that” (Bullis 2011a). As noted above, the history of sodium-cooled reactor costs, discussed briefly above, provides little reason to believe that thisexpectation will be realized.

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Even more optimistically, TWR proponents aim to have a demonstration reactor operating by 2022 and the first commercial reactor by the late 2020s (TerraPower 2013b).
This is an impossible schedule, at least for the United States. The TWR design, likeother sodium-cooled reactors, is so different from presently licensed reactors that
the Nuclear Regulatory Commission will have to write regulations specifically tailored for them. For instance, accident mechanisms in sodium-cooled
TerraPower is reportedly exploring
breeders are different than in lightagreements with China and India even though water reactors. It will take years for
the Nuclear Regulatory CommisChina has little experience with sodiumsion to staff up and acquire the necdata and expertise to write
cooled breeder reactors and India’s record so essary
the rules and do the safety and risk
evaluations. As a result, certificafar hardly inspires confidence, having beention and licensing of a demonstraplagued by leaks and accidents.
tion reactor design is likely to takemuch longer than proponents haveallowed for so far. Perhaps that is why TerraPower is reportedly exploring agreementswith China and India (Bullis 2011b) even though China has little experience withsodium-cooled breeder reactors5 and India’s record so far hardly inspires confidence,
having been plagued by leaks and accidents. Further, like other countries, such as
France and Japan, that have pursued dreams of breeder reactors becoming a mainstayof electricity supply, India’s breeder ambitions have suffered repeated setbacks anddelays (Ramana 2012).
But even if the most optimistic schedules are met, TWRs are at significant risk of being economically and technologically obsolete around the time of commercialization.
First, they will be unlikely to compete with existing nuclear reactor designs because
uranium is not a scarce resource and will not be for many decades. Second, distributed technologies, such as solar photovoltaics, microturbines, demand response, andstorage are developing so fast that they present a “disruptive challenge” to the utility
industry, as cell phones did to landlines. This is increasingly realized by the electricutility industry itself, as can be seen in a report by the industry’s Edison Electric Institute published in January 2013 (EEI 2013).
A critical resource consideration has not entered the TWR discussion yet. The TWR
is a thermal generation technology that, like today’s reactors and coal-fired power
plants, uses a lot of water. Each present-day 1,000 megawatt reactor evaporates between ten and twenty million gallons of water a day, with water intake requirementsin the hundreds of millions of gallons a day. Water is far more likely to be a critical
5 China has just one pilot-scale sodium-cooled reactor (65-megawatts thermal) which went critical in2010 (World Nuclear Association 2013).

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Traveling Wave Reactors: Sodium-cooled Gold at the End of a Nuclear Rainbow?

resource in the coming decades – much more so than uranium. Higher efficiency can
reduce this water requirement modestly, but solar PV and wind energy use essentiallyno water by comparison.
By focusing on the uranium resource issue, which is an economic non-problem forthe foreseeable future (which one can reasonably define as less than 100 years given
the scale and character of technological, economic, and security changes since 1913,
the eve of World War I), TWR proponents have lost sight of the practical problems
that have prevented commercialization of sodium-cooled breeders despite immense
effort and expense over more than six decades. They have also not taken adequate account of the twenty-first century low-carbon distributed, renewable smart grid that isalready emerging and that will likely become the center of the electricity system overthe next two to three decades.
For a list of IEER funders, please visit our website, www.ieer.org.
Acknowledgements: Thanks to M.V. Ramana of Princeton University for reviewing
this paper. Only the author is responsible for any errors, of course.

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Experimental Breeder Reactor II Operating Floor

Source: Argonne National Laboratory, at http://commons.wikimedia.org/wiki/File:EBR-II_-_Reactor_
operating_floor.jpg

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