Nuclear fusion is often seen as a promising technology for large-scale base-load power production and ITER is the international research project that should prove nuclear fusion is possible. On November 18, the ITER Council, the Governing Body of the ITER Organization, convened for its fifth meeting in Cadarache in southern France. At the 4th ITER Council meeting in June it was announced that the date for the first Deuterium-Tritium experiments is now 2026. So, the original plans from 2005 are even before any serious construction has started, already delayed by four years. However, according to an October 13, 2009 article in Nature, construction at the site of ITER has been at a standstill since April this year. Construction won't begin until 2010.

What follows is a reproduction of part of a new publication and concludes that the accumulated knowledge about nuclear fusion is already large enough to conclude that commercial fusion power is not only 50 years away but that it will always be 50 years away.

After the Second World War, many nuclear pioneers expected that nuclear fusion would provide their grandchildren with cheap, clean and essentially unlimited energy. Generations of physicists and physics teachers have been taught at the university, and have gone on to teach others, a) that progress made in fusion research is impressive, b) that controlled fusion is probably only a few decades away and c) that - given sufficient public funding - no major obstacles stand between us and success in this field.

Here are some quotes from physics textbooks that reflect this sort of optimism:

• “The goal seems to be visible now” (Nuclear and Particle Physics; Frauenfelder and Henley 1974)
• “It will most likely take until the year 2000 to bring a laboratory reactor to full commercial utilization” (Energy, Resources and Policy; R.Dorf 1978)
• “As the construction of a fusion reactor implies a large number of unsolved practical problems, one can not expect that fusion will become a usable energy resource during some decades! Within a longer time scale however it seems possible!” (Physics, P.A. Tipler 1991)

Obviously this has not happened yet; the fusion optimists have become more modest saying “if everything goes well, the first commercial fusion reactor prototype might be ready in 50 years from now”

Such statements only hide the fact that today we have no idea how to solve the remaining problems. The uncritical media of today waxed enthusiastically about the recent decision by the “world’s leaders” to provide the ten billion dollars needed to start the ITER fusion project [see ITER box].

The public, worried about global warming and oil price explosions, seems to welcome the tacit message that “we - the fusion scientists, the engineers, and the politicians - do everything that needs to be done to bring fusion energy on line before fossil fuel supplies become an issue, and before global warming boils us all.”

In what follows we challenge the assumption that the ITER project has any relation to the energy problem and we quantify the arguments of fusion sceptics. We start our discussion with an overview of the remaining huge problems facing commercial fusion and give a detailed description of why the imagined self-sufficient tritium breeding cycle can not work. In fact, as we are about to see, it seems that enough knowledge has been accumulated on this subject to safely conclude that whatever might justify the 10 billion dollar ITER project, it is not energy research.

Remaining barriers to fusion energy

Producing electricity from controlled nuclear fusion would require overcoming at least four major obstacles. The removal of each obstacle would need major scientific breakthroughs before any reasonable expectation might be formed of building a commercial prototype fusion reactor. It should be alarming that at best only the problems concerning the plasma control, described in point one below, might be investigated within the scope of the ITER project. Where and how the others might be dealt with is anyone’s guess.

These are the four barriers:

*1. Commercial energy production requires steady state fusion conditions for a deuterium-tritium plasma on a scale comparable to that of today’s standard nuclear fission reactors with outputs of 1 GW (electric) and about 3 GW(thermal) power. The current ITER proposal foresees a thermal power of only 0.4 GW using a plasma volume of 840 m3. Originally it was planned to build ITER with a plasma volume of 2000 m3 corresponding to a thermal fusion power of 1.5 GW, but the fusion community soon realized that the original ITER version would never receive the required funding. Thus a smaller, much less ambitious version of the ITER project was proposed and finally accepted in 2005.

The 1 GW(el) fission reactors of today function essentially in a steady state operation at nominal power and with an availability time over an entire year of roughly 90%. The deuterium-tritium fusion experiments have so far achieved short pulses of fusion power of 15 MW(therm) for one second and 4 MW(therm) for 5 seconds corresponding to a liberated thermal energy of 5 kWh [*1]. The Q value - produced energy over input energy - for these pulses was 0.65 and 0.2 respectively.

If everything works according to the latest plans [*2], it will be 2018 when the first plasma experiments can start with ITER. From there it will take us to 2026, at least another eight years, before the first tritium experiments are tried [The original plans from 2005 are now, even before any serious construction has started, already delayed by four years]. In other words it will take at best 20 years from the agreement by the world’s richest countries to construct ITER before one can find out if the goals of ITER, a power output of 0.5 GW(therm) with a Q value of up to 10 and for 400 seconds, are realistic. Compare that to the original ITER proposal which was 1.5 GW(therm), with a Q value between 10-15 and for about 10000 seconds. ITER proponents explain that the achievement of this goal would already be an enormous success. But this goal, even if it can be achieved by 2026, pales in comparison with the requirements of steady state operation, year after year, with only a few minor controlled interruptions.

Previous deuterium-tritium experiments used only minor quantities of tritium and yet lengthy interruptions between successive experiments were required because the radiation from the tritium decay was so excessively high. In earlier fusion experiments, such as JET, the energy liberated in the short pulses came from burning (fusing) about 3 micrograms (3 × 10−6 grams) of tritium, starting from a total amount of 20 gr of tritium. This number should be compared with the few kilograms of tritium required to perform the experiments foreseen during the entire ITER lifetime and still greater quantities that would be required for a commercial fusion reactor. A 400 second fusion pulse with a power of 0.5 GW corresponds to the burning of 0.035 gr (3.5×10−2 grams) of tritium.

A very large number when compared to 3 micrograms, but a tiny number when compared with the yearly burning of 55.6 kilograms of tritium in a commercial 1 GW(therm) fusion reactor.

The achieved efficiency of the tritium burning (i.e., the amount that is burned divided by the total amount required to achieve the fusion pulse) was roughly 1 part in a million in the JET experiment and is expected to be about the same in the ITER experiments, far below any acceptable value if one wants to burn 55.6 kg of tritium per year.

Moreover, in a steady state operation the deuterium-tritium plasma will be “contaminated” with the helium nucleus that is produced and some instabilities can be expected. Thus a plasma cleaning routine is needed that would not cause noticeable interruptions of production in a commercial fusion plant. ITER proponents know that even their self-defined goal (a 400 second long deuterium-tritium fusion operation within the relatively small volume of 840 m3) presents a great challenge. One might wonder what they think about the difficulties involved in reaching steady state operation for a full scale fusion power plant.

*2. The material that surrounds and contains thousands of cubic meters of plasma in a full-scale fusion reactor has to fulfill two requirements. First, it has to survive an extremely high neutron flux with energies of 14 MeV, and second, it has to do this not for a few minutes but for many years. It has been estimated that in a full-scale fusion power plant the neutron flux will be at least 10-20 times larger than in today’s state of the art nuclear fission power plants. Since the neutron energy is also higher, it has been estimated that - with such a neutron flux - each atom in the solid surrounding the plasma will be displaced 475 times over a period of 5 years [*3]. Second, to further complicate matters, the material in the so called first wall (FW) around the plasma will need to be very thin, in order to minimize inelastic neutron collisions resulting in the loss of neutrons (for more details see next section), yet at the same time thick enough so that it can resist both the normal and the accidental collisions from the 100-million-degree hot plasma and for years.

The “erosion” for carbon-like materials from the neutron bombardment has been estimated to be about 3 mm per “burn” year and even for materials like tungsten it has been estimated to be about 0.1 mm per burn year [*3].

In short, no material known today can even come close to meeting the requirements described above. Exactly how a material that meets these requirements could be designed and tested remains a mystery, because tests with such extreme neutron fluxes can not be performed either at ITER or at any other existing or planned facility.

*3. The radioactive decay of even a few grams of tritium creates radiation dangerous to living organisms, such that those who work with it must take sophisticated protective measures. Moreover, tritium is chemically identical to ordinary hydrogen and as such very active and difficult to contain. Since tritium is also a necessary ingredient in hydrogen fusion bombs, there is additional risk that it might be stolen. So, handling even few kg of tritium foreseen for ITER is likely to create major headaches both for the radiation protection group and for those concerned with the proliferation of nuclear weapons.

Both of these challenges are essentially ignored in the ITER proposal and the only thing the protection groups have to work with today are design studies based on computer simulations. This may not be of concern to the majority of ITER’s promoters today, since they will be retiring before the tritium problem starts in something like 10 to 15 years from now [*4]. But at some point it will become a greater challenge also for ITER and especially once one starts to work on a real fusion experiment with many tens of kilograms of tritium.

*4. Problems related to tritium supply and self-sufficient tritium breeding will be discussed in detail in section 'The illusion of tritium self-sufficiency'. But first it will be useful to describe qualitatively two problems that seem to require simultaneous miracles if they are to be solved.

* The neutrons produced in the fusion reaction will be emitted essentially isotropically in all directions around the fusion zone. These neutrons must somehow be convinced to escape without further interactions through the first wall surrounding the few 1000 m3 plasma zone. Next, the neutrons have to interact with a “neutron multiplier” material like beryllium in such a manner that the neutron flux is increased without transferring too much energy to the remaining nucleons. The neutrons then must transfer their energy without being absorbed (e.g. by elastic scattering) to some kind of gas or liquid, like high pressure helium gas, within the lithium blanket. This heated gas has to be collected somehow from the gigantic blanket volume and must flow to the outside. This heat can be used as in any existing power plant to power a generator turbine. This liquid should be as hot as possible, in order to achieve reasonable efficiency for electricity production. However, it is known that the lithium blanket temperature can not be too high; this limits the efficiency to values well below those from today’s nuclear fission reactors, which also do not have a very high efficiency.

Once the heat is extracted and the neutrons are slowed sufficiently, they must make the inelastic interaction with the Li-6 isotope, which makes about 7.5% of the natural lithium. The minimal thickness of the lithium blanket that surrounds the entire plasma zone has been estimated to be at least 1 meter. Unfortunately, lithium like hydrogen (tritium atoms are chemically identical to hydrogen) in its pure form is chemically highly reactive. If used in a chemical bound state with oxygen, for example, the oxygen itself could interact and absorb neutrons, something that must be avoided. In addition, lithium and the produced tritium will react chemically - which is certainly not included in any present computer modeling – and some tritium atoms will be blocked within the blanket. Unfortunately, additional neutron and tritium losses can not be allowed as will be described in more detail in section 'The illusion of tritium self-sufficiency'.

• Next, an efficient way has to be found to extract the tritium quickly, and without loss, from this lithium blanket before it decays. We are talking about a huge blanket here, one that surrounds the few 1000 m3 plasma volume. Extracting and collecting the tritium from this huge lithium blanket will be very tricky indeed, since tritium penetrates thin walls relatively easily, and since accumulations of tritium are highly explosive. (An interesting description of some of these difficulties that have already been encountered in a small scale experiment can be found in reference [*5].)

Finally assuming we get that far, the extracted and collected tritium and deuterium, which both need to be extremely clean, need to be transported, without losses, back to the reactor zone.

Each of the unsolved problems described above is, by itself, serious enough to raise doubts about the success of commercial fusion reactors. But the self- sufficient tritium breeding is especially problematic, as will be described in the next section.

The illusions of tritium self-sufficiency

The fact is, a self-sustained tritium fusion chain appears to be not simply problematic but absolutely impossible. To see why, we will now look into some details based on what is already known about this problem.

A central quantity for any fission reactor is its criticality, namely that exactly one neutron, out of the two to three neutrons “liberated” per fission reaction, will enable another nuclear fission reaction. More than 99% of the liberated fission energy is taken by the heavy fission products such as barium and krypton and this energy is relatively easily transferred to a cooling medium. The energy of the produced fission neutrons is about 1 MeV. In order to achieve the criticality condition, the surrounding material must have a very low neutron absorption cross section and the neutrons must be slowed down to eV energies. For a self-sustained chain reaction to happen, a large amount of U235, enriched to 3-5%, is usually required. Once the nominal power is obtained, the chain reaction can be regulated using materials with a very high neutron absorption cross section.

In contrast to fission reactions, only one 14 MeV neutron is liberated in the D + T - He + n fusion reaction. This neutron energy has to be transferred to a medium using elastic collisions. Once this is done, the neutron is supposed to make an inelastic interaction with a lithium nucleus, splitting it into tritium and helium.

Starting with the above reaction one can calculate how much tritium burning is required for continuously operating commercial fusion reactor assuming a power production of 1 GW(thermal)[This is relatively small compared to standard 3 GW(thermal) fission reactors which achieve up to 95% steady state operation]. One finds that about 55.6 Kg of tritium needs to be burned per year with an average thermal power of 1 GW.

Today tritium is extracted from nuclear reactors at extraordinary cost - about 30 million US dollar per kg from Canadian heavy water reactors. These old heavy water reactors will probably stop operation around the year 2025 and it is expected that a total tritium inventory of 27 kg will have been accumulated by that year [*6]. Once these reactors stop operating, this inventory will be depleted by more than 5% per year due to its radioactive decay alone -tritium has a half-life of 12.3 years. As a result, for the prototype “PROTO” fusion reactor, which fusion optimists imagine to start operation not before the year 2050, at best only 7 kg of tritium might remain for the start (Normal fission reactors produce at most 2-3 kg per year and the extraction costs have been estimated to be 200 million dollars per kg [*6].). It is thus obvious that any future fusion reactor experiment beyond ITER must not only achieve tritium self-sufficiency, it must create more tritium than it uses if there are to be any further fusion projects. The particularly informative website of professor Abdou from UCLA, one of the world’s leading experts on tritium breeding, gives some relevant numbers both about the basic requirements for tritium breeding and the state of the art today [*7].

But first things first: Understanding such “expert” discussions requires an acquaintance with some key terms:

•  The “required tritium breeding ratio”, rTBR, stands for the minimal number of tritium nuclei which must be produced per fusion reaction in order to keep the system going. It must be larger than one, because of tritium decay and other losses and because of the necessary inventory in the tritium processing system and the stockpile for outages and for the startup of other plants. The rTBR value depends on many system and technology parameters.

•  The “achievable tritium breeding ratio”, aTBR, is the value obtained from complicated and extensive computer simulations - so-called 3-dimensional simulations - of the blanket with its lithium and other materials. The aTBR value depends on many parameters like the first wall material and the incomplete coverage of the breeding blanket.

•  Other important variables are used to define quantitatively the value of the rTBR. These include: (1) the “tritium doubling time”, the time in years required to double the original inventory; (2) The “fractional tritium burn up” within the plasma, expected to be at best a few %; (3) The “reserve time”, the tritium inventory required in days to restart the reactor after some system malfunctioning with a related tritium loss; and (4) The ratio between the calculated and the experimentally obtained TBR.

The handling of neutrons, tritium and lithium requires particular care, not only because of radiation, but also because tritium and lithium atoms are chemically very reactive elements. Consequently, real-world, large-scale experiments are difficult to perform and our understanding of tritium breeding is based almost entirely on complicated and extensive computer simulations, which can only be done in a few places around the world.

Some of these results are described in a publication by Sawan and Abdou from December 2005 [*8]. The authors assume that a commercial fusion power reactor of 1.5 GW (burning about 83 kg of tritium per year) would require a long-term inventory of 9 kg and they further assume that the required start-up tritium is available.

They argue that according to their calculations, the absolute minimum rTBR is 1.15, assuming a doubling time of more than 4 years, a fractional tritium burn-up larger than 5% and a reserve time of less than 5 days. Requiring a shorter doubling time of 1 year, their calculations indicate that the rTBR should be around 1.5. Other numbers can be read from their figures. For example one finds that if the fractional burn-up would be 1% the rTBR should be 1.4 for a 5 year doubling time and even 2.6 for a 1 year doubling time. To compare: the fractional tritium burn-up during the short MW pulses in JET was roughly 0.0001%.

The importance of short tritium doubling times can be understood easily using the following calculation. Assuming these numbers can be achieved and that 27 kg tritium (2025) minus the 9 kg long term inventory, would be available at start-up, then 18 kg could be burned in the first year. A doubling time of 4 years would thus mean that such a commercial 1.5 GW(thermal) reactor can operate at full power only 8 years after the start-up.

And if anything these rTBR estimates are far too optimistic since a number of potential losses related to the tritium extraction, collection and transport are not considered in today’s simulations.

The details become even more troubling when we turn to the tritium breeding numbers that have been obtained with computer simulations.

After many years of detailed studies, current simulations show that the blanket designs of today have, at best, achieved TBR’s of 1.15. Using this number, Sawan and Abdou conclude that theoretically a small window for tritium self-sufficiency still exists. This window requires (1) a fractional tritium burn up of more than 5%, (2) a tritium reserve time of less than 5 days and (3) a doubling time of more than 4 years. But using these numbers, the authors believe it is difficult even to imagine a real operating power plant. In their words, “for fusion to be a serious contender for energy production, shorter doubling times than 5

years are needed”, and the fact is, doubling times much shorter than 5 years appear to be required, which means TBR’s much higher than 1.15 are necessary. To make matters worse, they also acknowledge that current systems of tritium handling need to be explored further. This probably means that the tritium extraction methods from nuclear fission reactors are nowhere near meeting the requirements.

Sawan and Abdou also summarize various effects which reduce the obtained aTBR numbers once more realistic reactor designs are studied and structural materials, gaps, and first wall thickness are considered. For example they find that as the first wall, made of steel, is increased by 4 cm starting from a 0.4 cm wall, the aTBR drops by about 16%. It would be interesting to compare these assumptions about the first wall with the ones used in previous plasma physics experiments like JET and the one proposed for ITER. Unfortunately, we have so far not been able to obtain any corresponding detailed information. However,

as it is expected that the first wall in a real fusion reactor will erode by up to a few mm per fusion year, the required thin walls seem to be one additional impossible assumption made by the fusion proponents.

Other effects, as described in detail by Sawan and Abdou [*8], are known to reduce the aTBR even further. The most important ones come from the cooling material required to transport the heat away from the breeding zone, from the electric insulator material, from the incomplete angular coverage of the inner plasma zone with a volume of more than 1000 m3 and from the plasma control requirements.

This list of problems is already very long and shows that the belief in a self-sufficient tritium chain is completely unfounded. However, on top of that, some still very idealized TBR experiments have been performed now. These real experiments show, according to Sawan and Abdou [*8], that the measured TBR results are consistently about 15% lower than the modeling predicts. They write in their publication: “the large overestimate (of the aTBR) from the calculation is alarming and implies that an intense R&D program is needed to validate and update .. our ability to accurately predict the achievable TBR.”

One might conclude that a correct interpretation could have been:

Today’s experiments show consistently that no window for a self-sufficient tritium breeding currently exists and suggest that proposals that speak of future tritium breeding are based on nothing more than hopes, fantasies, misunderstandings, or even intentional misrepresentations.

Ending the dreams about controlled nuclear fusion

As we have explained above, there is a long list of fundamental problems concerning controlled fusion. Each of them appears to be large enough to raise serious doubts about the viability of the chosen approach to a commercial fusion reactor and thus about the 10 billion dollar ITER project.

Those not familiar with the handling of high neutron fluxes or the possible chemical reactions of tritium and lithium atoms might suppose that these problems are well known within the fusion community and are being studied intensively. But the truth is, none of these problems have been studied intensively and, at best, even with the ITER project, the only problems that might be studied relate to some of the plasma stability issues outlined in section 'Remaining barriers to fusion energy'. All of the other problem areas are essentially ignored in today’s discussions among “ITER experts”.

Confronted with the seemingly impossible tritium self-sufficiency problem that must be solved before a commercial fusion reactor is possible, the “ITER experts” change the subject and tell you that this is not a problem for their ITER project. In their view it will not be until the next generation of experiments - experiments that will not begin for roughly another 30 years according to official plans - that issues related to tritium self-sufficiency will have to be dealt with. Perhaps they are also comfortable with the fact that neither the problems related to material aging due to the high neutron flux nor the problems related to tritium and lithium handling can be tested with ITER. Perhaps they expect miracles from the next generation of experiments.

However among those who are not part of ITER and those who do not expect miracles, it seems that times are changing. More and more scientists are coming to the conclusion that commercial fusion reactors can never become reality. Some are even receiving a little attention from the media as they argue louder and louder that the entire ITER project has nothing to do with energy research [*9].

One scientist who should be receiving more attention than he is, is Professor Abdou. In a presentation in 2003 that was prepared on behalf of the US fusion chamber technology community for the US Department of Energy (DOE) Office of Science on Fusion Chamber Technology he wrote that “Tritium supply and self-sufficiency are ‘Go-No Go’ issue for fusion energy, [and are therefore] as critical NOW as demonstrating a burning plasma” [capitalization in original]. He pointed out that “There is NOT a single experiment yet in the fusion environment that shows that the DT fusion fuel cycle is viable. He said that “Proceeding with ITER makes Chamber Research even more critical” and he asked “What should we do to communicate this message to those who influence fusion policy outside DOE?” [*10]. In short, to go ahead with ITER without addressing these chamber technology issues makes no sense at all. In light of everything that has been said in this section, it seems clear that this is what should be done:

Tell the truth to the tax payers, the policy makers and to the media; tell them that, after 50 years of very costly fusion research conducted at various locations around the world, enough knowledge exits to state:

1. that today’s achievements in all relevant areas are still many orders of magnitude away from the basic requirements of a fusion prototype reactor;

2. that no material or structure is known which can withstand the extremely high neutron flux expected under realistic deuterium-tritium fusion conditions; and

3. that self-sufficient tritium breeding appears to be absolutely impossible to achieve under the conditions required to operate a commercial fusion reactor.

It is late, but perhaps not too late, to acknowledge that the ITER project is at this point nothing more than an expensive experiment to investigate some fundamental aspects of plasma physics. Since this would in effect acknowledge that the current ITER funding process is based on faulty assumptions and that ITER should in all fairness be funded on equal terms with all other research projects, acknowledging these truths will not be easy. But it is the only honest thing to do.

It is also the only path that will allow us to transfer from ITER to other more promising research the enormous resources and the highly skilled talents that need now to be brought to bear on our increasingly urgent energy problems. In short, this is the only path that will allow us to stop “throwing good money after bad” and to start dealing with our emerging energy crisis in a realistic way.

References:
[*1] See for example John Wesson, The Science of JET, March 2000 at http://www.jet.efda.org/documents/books/wesson.pdf and chapter 14 and Appendix I for the timeline of the JET experiments.
[*2] The new, four year delayed date for the first Deuterium-Tritium experiments in 2026 has been announced at the 4th ITER Council meeting in June 2009 as described at http://www.iter.org/proj/Pages/ITERMilestones.aspx. However, it seems that nothing goes as planned. According an article in Nature, October 13, 2009, ITER is at a standstill since April
[*3] For some more details see the presentation by B. D. Wirth, www.nuc.berkeley.edu/courses/classes/NE39/Wirth-FusionMaterials lecture2.pdf and by S. J. Zinkle (2004) page 47 http://fire.pppl.gov/aps dpp04 zinkle.pdf.
[*4] It seems that the ITER people are working on a new quantitative construction and operation timeline as details are currently not specified on the ITER homepage. However a qualitative overview can be be found at http://www.iter.org/PROJ/Pages/ITERAndBeyond.aspx. The original 50 year timeline towards the realization of the DEMO and PROTO fusion devices are described at http://www.fusion.org.uk/culham/fasttrack.pdf.
[*5] J. L. Anderson; Journal of fusion Energy, Vol 4, Nos. 2/3, 1985 and www.springerlink.com/content/m34445687252l544/.
[*6] See for example M. Abdou, Notes for Informal Discussion with Senior Fusion Leaders in Japan (JAERI and Japanese Universities”, March 24, 2003.
[*7] The website of Prof. M. Abdou; www.fusion.ucla.edu/abdou/.
[*8] M. E. Sawan and M. A. Abdou; Fusion Engineering and Design 81 (2006) 1131.
[*9] See for example S. Balibar, Y. Pomeau and J. Treiner in Le Monde, 24/25 October 2004 and W. E. Parkins, Fusion Power: will it ever come, March 10 Science Vol 311 and http://fire.pppl.gov/fusion science parkins 031006.pdf.
[*10] M. Abdou, briefing to DOE Office of Science, Washington June 3, 2003 at www.fusion.ucla.edu/abdou/abdou%20presentations/2003/orbach%20pres%20(6-1-03)%20Final1.ppt.

Source and contact: The Future of Nuclear Energy: Facts and Fiction. Chapter IV: Energy from Breeder Reactors and from Fusion? (13 November 2009), Michael Dittmar, Institute of Particle Physics, ETH, 8093 Zurich, Switzerland.

The whole chapter is available at: http://arxiv.org/PS_cache/arxiv/pdf/0911/0911.2628v1.pdf

 

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