By 2017 the
Chinese are expecting to be running an experimental molten salt reactor, whilst other countries and commercial organisations,
are being left behind. China’s first step towards liquid fuelled thorium reactors is, in essence, to reproduce the work done by Oak Ridge National Nuclear Laboratory (ORNL) in the sixties, when ORNL built and ran the Molten Salt Reactor Experiment MSRE. But what are the
problems and challenges facing the Chinese as front runners in the drive to start
up a liquid fuelled thorium reactor (LFTR)?
Alvin Weinberg |
Under Director Alvin Weinberg, back in the sixties
and seventies a number of them were identified by the MSRE at Oak Ridge National Nuclear Laboratory. In the test environment some of these challenges seemed to have answers, whilst
others are still to be solved. They are
all written up in reports and published papers, now freely available on the
internet, or at the ORNL archives. You
can be sure that they have been well studied by the many Chinese visitors to
Oak Ridge.
Materials Hastelloy - N
The MSRE ran at around 670 deg C and the combination of high temperature and radiation made the selection of materials critically important.
The Molten Salt Reactor Experiment |
• Carbon
0.04-0.08
• Chromium
6.00-8.00
• Molybdenum
15.00-18.00
• Iron
5.00 max
• Manganese
0.8 max
• Aluminum
+ Ti 0.5 max
• Boron
0.01 max
• Sulfur
0.03 max
• Nickel
remainder
During construction questions arose concerning the
stress-rupture life and fracture strain, which were found to be
drastically reduced by thermal neutron irradiation.
An out-of-pile corrosion test program was carried out for
Hastelloy-N[9] which
indicated extremely low corrosion rates at MSRE conditions. Capsules exposed in the Materials
Testing Reactor showed that salt fission power densities of more than 200 W/cm3 had
no adverse effects on compatibility of fuel salt, Hastelloy-N, and
graphite. With their chosen salt
mixture (see below) and at the operating temperature, they found that Hastelloy
N was adequately resistant against corrosion and embrittlement for its design
life in the MSRE. Since this was an
experimental reactor, however, this is not the same as saying that it will last
the 30 years necessary for a commercial reactor.
Later experience showed that the mechanical properties of
Hastelloy – N do deteriorate as a result of exposure to thermal neutrons but that
the addition of small amounts of titanium and hafnium significantly improve its
performance. to select the most resistant alloy much more long term operational experience is needed.
MSRE core |
Graphite Moderator
As in Light Water Reactors, the graphite moderator blocks were found to swell and crack in the high radiation environment. As a minimum this creates a maintenance issue since the blocks have to be replaced. More seriously, depending on the reactor design, it can block fluid pathways and lead to hot spots.
As in Light Water Reactors, the graphite moderator blocks were found to swell and crack in the high radiation environment. As a minimum this creates a maintenance issue since the blocks have to be replaced. More seriously, depending on the reactor design, it can block fluid pathways and lead to hot spots.
Research into graphite production methods and
coatings was carried out by ORNL but it remained an unsolved problem in the
early seventies.
There are many ways to design a nuclear reactor and
other possibilities of moderating the neutron flux may need to be tried.
Alternatively one could opt for an un-moderated molten
salt reactor design working in the fast spectrum. Such a reactor would be able to burn
actinides and eliminate almost entirely the production of highly radioactive
waste having a long half life. This is
the subject of research at Grenoble, France but it has never been attempted on the
scale of an experimental reactor so far.
Tritium
removal
Tritium is
generated in small quantities within the molten salt as a breakdown product of lithium
6. Tritium, or hydrogen-3, is
made by bombarding lithium-6 (6Li)
with a neutron (n). This
neutron bombardment will cause the lithium-6 nucleus to fission,
producing helium-4 (4He)
plus tritium (3T) and energy.
Tritium is highly radioactive and must be sequestered in a
secure storage facility. If, however,
the lithium salt used is purified to 99.995% Lithium -7, then the quantities of
tritium produced amount to only a few hundred grams per year from a 1GWe
reactor.
At the temperatures concerned, however, tritium can pass
through the heat exchanger material and get into the secondary cooling loop
from where it could escape into the environment. ORNL developed a secondary loop coolant
system that would chemically adsorb the few hundred grams of residual tritium
to a less mobile form, so that it could be trapped and removed from the
secondary coolant, rather than diffusing into the turbine power cycle. ORNL calculated that this technique would, by
itself, reduce tritium emissions to the environment to acceptable levels
The tritium was then extracted and successfully
oxidized over copper oxides and captured in a pair of water bubblers. No tritium was found in the exhaust
gases.
The process of capturing the already low
concentration of tritium from the molten salt was found to be not very
straightforward and more work is need to develop this or other process options.
The Lithium
Problem
ORNL chemists did extensive pioneering work to find
the best mixture of salts to give the desired physical and chemical
characteristics. Many were tested but
they opted for Flibe, a mixture of lithium and beryllium fluorides.
Present day research programmes may need to revisit
the choice of lithium because it’s necessary to use only lithium 7 and to remove
the 7.5 % of the naturally present lithium 6 isotope. Otherwise, depending on the concentration,
lithium 6 would either transmute in the reactor into tritium, as mentioned
above, or prevent the reactor from starting up due to its high neutron
absorption characteristics.
But this is only part of the lithium problem. At present only two countries are carrying out
lithium isotope separation, China and Russia.
Since lithium 6 can be used to make tritium its
production is strictly monitored.
Interestingly in the US Castle Bravo hydrogen bomb,
tested at Bikini Atoll on 1st March 1954, it was assumed that only the
30% of lithium-6 present in the lithium charge would react in a hydrogen bomb, but
the contribution from an overlooked reaction due to the presence of the
remaining 70% of lithium-7 caused an
unexpected increase in yield of 250%, making the 15 Megaton explosion the largest thermonuclear device tested at that
date.
The US stopped separation of these isotopes, using
the mercury amalgam method, a number of years ago due to concerns about its
toxicity and the fact that large quantities of mercury had been lost from the
Oak Ridge National Nuclear Laboratory inventory in an unknown manner.
So the lithium problem presents a difficulty to any
private sector group not working in co-operation with a government having a form
of lithium isotope separation technology.
Other salt mixtures not using lithium are possible and
many were tested at ORNL in the laboratory but so far they are
completely untested in reactors and may affect the choice of reactor materials.
Storage of Solidified Salts
At
the end of the MSRE programme the molten salts were stored as a solidified
material. It was found that fluorine and uranium hexafluoride were continuously released by radiolysis. As a temporary measure the solidified contents were periodically reheated to
induce recombination, but eventually the uranium was removed from the salts in
an expensive and challenging cleanup programme.
A solution to this problem would be to remove the uranium prior to
storage of the solidified salt by sparging the molten salt with fluorine gas,
to create uranium hexafluoride which can be re-introduced into the reactor.
Plutonium must also be removed to prevent radiolysis, which can be done by the addition
of sodium carbonate to create plutonium dioxide.
Conclusion
This
is by no means a full list of the issues which arose during the operation of
the MSRE. (Section 7 of the Weinberg Foundation's recent Report on Thorium-Fuelled Molten Salt Reactors gives several more). So there are plenty of
technical challenges to address as the Chinese firstly repeat the MSRE
experiment, and then extend it into larger reactor designs. Personally I’m extremely pleased that the
Chinese have the vision, the money and the forward thinking to restart and
extend the pioneering work that was done at ORNL in the sixties and seventies The use of thorium
reactors running at atmospheric pressure will be much safer and will produce
much less radioactive wastes than the current 50 year old designs of the existing Light Water Reactor
fleet. For me safe and abundant nuclear
power is the only way of avoiding the prospect of runaway global warming, because conservation of energy, and the intermittent nature of the main renewable sources, cannot provide more than a part of the answer to the rapidly increasing global demand for energy.
Under Weinberg's leadership ORNL had a world leading combination of nuclear scientists, engineers, chemists and metallurgists all working under one organisational umbrella. They were capable of taking any brief concerning nuclear power generation and turning it into reality quickly and efficiently. The USA allowed much of this expertise to dissipate when the Nixon administration fired Alvin Weinberg because he disagreed with the administration’s chosen programme of liquid metal cooled fast breeder reactors. By the time that programme was closed down the USA had forgotten about the highly promising liquid fluoride technology that is once again coming to the fore.
Under Weinberg's leadership ORNL had a world leading combination of nuclear scientists, engineers, chemists and metallurgists all working under one organisational umbrella. They were capable of taking any brief concerning nuclear power generation and turning it into reality quickly and efficiently. The USA allowed much of this expertise to dissipate when the Nixon administration fired Alvin Weinberg because he disagreed with the administration’s chosen programme of liquid metal cooled fast breeder reactors. By the time that programme was closed down the USA had forgotten about the highly promising liquid fluoride technology that is once again coming to the fore.
It’s
a pity that the US, like other western countries, has not yet found the courage
or political will to overcome the inertia inherent in the nuclear
establishment, which is committed to the Pressurised Light Water Reactor and the
uranium–plutonium fuel cycle. Coming
from the UK, I’ve seen many examples over the years where pioneering research is done by
underfunded organisations, only to be developed by other better placed
countries. It’s a symptom of the West’s debt-burdened
economic decadence in the face of the challenge of the Far East, but in fifty
years time, if all goes well, we’ll thank the Chinese for picking up and
developing ORNL’s 50 year old Liquid Fluoride Reactor research, even if we have
to pay the licence fees to China for our neighbourhood power station.
Although
there are some signs of increasing openness, and their thorium programme is a
good example, it’s also worrying that the Chinese, as communists, do not have a
fully representative form of government.
I sincerely hope that the Chinese thorium programme doesn't get caught
up in some sort of revolutionary “Chinese Spring” that could set their
programme back decades.
Here are some other posts that might interest you if you have read this far.
An outline of the Chinese thorium program given by Kun Chen,Professor and Deputy Director, Department of Nuclear Safety and Engineering, Shanghai Institute of Applied Physics.
http://johnpreedy.blogspot.fr/2012/08/the-chinese-thorium-programme.html
A detailed review of Robert Hargraves' book "Thorium- energy cheaper than coal".
http://johnpreedy.blogspot.fr/2012/11/thorium-energy-cheaper-than-coal.html
China has a virtual monopoly on the production of rare earth elements of which process thorium is a byproduct.
http://johnpreedy.blogspot.fr/2012/09/the-thorium-problem.html
Here are some other posts that might interest you if you have read this far.
An outline of the Chinese thorium program given by Kun Chen,Professor and Deputy Director, Department of Nuclear Safety and Engineering, Shanghai Institute of Applied Physics.
http://johnpreedy.blogspot.fr/2012/08/the-chinese-thorium-programme.html
A detailed review of Robert Hargraves' book "Thorium- energy cheaper than coal".
http://johnpreedy.blogspot.fr/2012/11/thorium-energy-cheaper-than-coal.html
China has a virtual monopoly on the production of rare earth elements of which process thorium is a byproduct.
http://johnpreedy.blogspot.fr/2012/09/the-thorium-problem.html