Nuclear Deal Revisited Part - II




1 RatingsJuly 30th, 2008
In my previous post I had highlighted the Qualitative Requirements (QRs) for the kind of Nuclear Reactors we need to address our growing demands of energy (primarily Electricity) in the face of dwindling non-renewable (read fossil fuel) energy sources and the growing global warming concerns. In this post I’d like to propose a (proven) Reactor design which is being seriously being considered as the most practical and perhaps the best alternative for future Nuclear power generation. This is the Molten Salt Reactor (MSR for short). I use the word proven since a small (8 Mega Watt) MSR has been successfully operated at the Oak Ridge National Laboratory, USA for nearly five year from 1964 to 1969. A Molten Salt Reactor represents a radical shift from conventional PWR or PHWR reactors. In this the fuel is mixed with a highly reactive salt, namely Fluoride. Salts as we know are solids at room temperature, but when they reach high temperature, the melt and flow like water. However, unlike water (which expands when it freezes i.e. turns to solid), salts do not expand when cooled to solid state. Hence, when a PWR or PHWR has to be operated at very HIGH PRESSURE, the MSR can be operated at much LOWER PRESSURE. The basic design of a MSR (as Googled from Wikipedia) is as shown below: - The molten Fluoride salt (mixed with Uranium Fuel) is made to flow through the reactor core which has Graphite as the moderator. The MSR experiment at Oak Ridge has used all the three types of Nuclear Fuels namely Uranium 235, Plutonium 239 and the Thorium U233 types. But it has been found to be most successful with the Thorium Fuel cycle. Since I have proposed that our target Reactor should use Thorium as the fuel, let us first understand how the Thorium Fuel Cycle works. Thorium Fuel Cycle Natural Thorium is predominantly available in its Isotope form of Th-232. Like I mentioned earlier, to commence any Nuclear Reaction, we require a source of Neutrons. One of the natural sources which produces Neutrons is Uranium 235. Uranium 235 naturally fissions and releases Neutrons and also energy. When Th-232 absorbs a Neutron, it emits a Beta Ray and transforms to another element Proactinium-233 (in about 22 minutes). After a period of about 27.7 days, this Proactinium-233 emits another Beta Ray and transforms itself into Uranium 233. Now, Uranium 233 is an excellent fissile material. It is a far more EFFICIENT fissile material than Uranium 235 or even Plutonium 239. How? When Uranium 233 encounters a low energy (thermal) Neutron, there is a 90% chance that it will fission to release energy (i.e. only 10% chance that it will not fission). When Uranium 235 encounters a low energy Neutron, there is less than 84% chance that it will fission (i.e. more than 16% chance that it will not fission) When Plutonium 239 encounters a low energy Neutron, there is only a 75% chance that it will fission (i.e. around 25% chance that it will not fission). As the temperature INCREASES, the fission capability of Uranium 235 or Plutonium 239 DECREASES, whereas the fission capability of Uranium 233 remains unchanged. In the MSR, in order to maximize the yield of fissile material, the Proactinium-233 which is produced is ‘extracted’ and stored separately (to protect it from Neutron bombardment) for about 27 days when almost all of it is converted to Uranium 233. This is then re-introduced into the MSR as fissile fuel. Therefore, with a proper mix of Th-232 and Uranium 233, we can sustain a Nuclear Reaction almost continously in the MSR, with Thorium (in the form of Th-232) as the only fuel input. Looking back at the MSR figure, we see that the molten salt fuel is passed through the Graphite moderator, where the Nuclear Reaction takes place i.e. where the Th-232 or Uranium 233 is made to ‘encounter’ a slow (thermal) Neutron. This will obviously generate energy within the Molten Salt, which will raise the temperature of the salt. In the figure, we can see two Heat-Exchangers which are used to extract the heat of the molten salt and use it to drive a Steam-Turbine. This turbine is coupled to a Generator which is used to generate electricity. Advantages of the Thorium Fuel Cycle Molten Salt Reactor Let us try and measure the advantages of this Thorium Cycle Molten Salt Reactor vis-à-vis the Qualitative Requirements which I had spelt out in my last post. 1. Thorium Fuel Based The reactor uses Thorium fuel cycle. India has the second largest Thorium resources in the world. 2. Compact Size & Inherent Safety. To understand how the MSR can be built in compact size, we have to look at two aspects namely, Low Pressure cycle (of Molten Salts) and Inherent safety features of the molten salt. As I described in my last post, in a PHWR or PWR, (as the name suggests) very high pressures are involved. Thus the reactors have to be built with thicker layers of materials. Moreover, to cater for the safety backups, the whole reactor complex has many layers of defenses. In the MSR, the molten salt is at low pressure (hence no danger of explosion). Due to the highly ionic nature of Fluorine, all the transmutation products (of the Nuclear Reaction) combine with the Fluorine and thus keep them out of circulation. The salts do not burn in air or water. The salts also do not dissolve in water. Even if there is leakage of the molten salt (to the atmosphere), it will solidify (due to loss of temperature) and ‘trap’ the radioactive elements inside. The readers may find it interesting to note, that the concept of Molten Salts for Nuclear Reactors was first thought of in the context of a Nuclear Powered Aircraft Engine (in the same Oak Ridge lab). Now, as we all know, an aircraft engine has to be really compact and light weight. Catch the drift? 2. Less Time Frame to Build and Commission. The compact size and the inherent Safety features will in essence reduce the time-frame to build small, distributed MSRs all over the country. 3. Higher ‘Burn’ Efficiency. The ‘burn’ efficiency of the Thorium cycle MSRs has been documented to be of the order of 97% and more. (Just compare that with PWR with an efficiency of only 2% and you can understand what I’m talking about) 4. Manageable Radioactive Residues. Conventional Nuclear Reactors produce residues with Half lives (the period after which the radioactivity level reduces to half) of the order of thousands of years. In case of Thorium cycle MSRs, the majority of the fission residues have half life of less than 100 years. In only about 300 years of storage, the residues will have less radioactivity than the ore from which Thorium was extracted! 5. Flexibility of Fuel Source. As we have seen, the MSR can use all types of fuel including Uranium 235, Plutonium 239 and Th-232. In fact it can also use the Transuranic waste of other reactors and other dismantled weapons etc. 6. Independence from NSG. Obviously, since there is no Fuel Fabrication involved, we don’t need to depend on the NSG for specialized fuel which is used in conventional reactor. In fact this has been listed as a DISADVANTAGE of MSRs since no supplier would be willing to supply ‘unfabricated’ fuel. However, as I said earlier, once a reaction is started in the Thorium cycle with initial fissile material (like Uranium 235), the MSR will generate adequate amount of Uranium 233 to sustain the reaction. 7. Lesser Operating Cost. As far as the operating costs are concerned, I would simply like to quote a study which was conducted in Lawrence Livermore National Laboratory, USA in 2001 (http://www.geocities.com/rmoir2003/COE_10_2_2001.doc) which compared the cost of electricity generation in a PWR, Coal based Plant and MSR. The results were 3.8, 4.1 and 4.2 ¢/kWh for MSR, PWR and Coal Plant respectively. (NOTE: It would be naïve to assume that the MSR Experiment at Oak Ridge did not face any problems and had a smooth sailing. However, it needs to be stated that: - (a) The MSR itself came about at the culmination of nearly 17 years of research which began in the US in the early 1950’s. (b) Almost all the problems which the Oak Ridge group encountered were resolved and in any case valuable lessons were learnt which would make any present day MSR that much better. (c) The numerous advantages far outweigh the few drawbacks which were encountered and corrected) Where Can I Get My MSR Technology? Now this is the most interesting question. Further, if this technology is so attractive, why aren’t people using it? The fact is that people are using it. In Japan, a 100 MWe MSR (FUJI) is being built in joint collaboration between Japan, US and Russia. In any case the expertise of the original MSR of Oak Ridge Lab is available in the US. I have found huge resources on the Internet, which give the Engineering details of the Oak Ridge MSR. Notwithstanding that, can’t we approach the concerned US agencies and BUY the technology? However, the pertinent question to ask here would be:- Do we require a Nuclear Deal with the US and the IAEA regime to get this technology from the US? As per my assessment, the answer to the above question is NO, we did not. Let me elaborate. The Thorium Cycle MSR is inherently NUCLEAR PROLIFERATION RESISTANT. This means, that if we are using a Thorium Cycle MSR, we CANNOT create Weapon Grade Plutonium! I wrote about the Uranium 233 which we were using as fissile material for the MSR. However, for making Nuclear Weapons we need Uranium 235 and Plutonium 239. Although in the MSR Plutonium 239 is produced in minute quantities, but due to its reaction with the Fluoride Salt it gets converted to non-weapon grade Plutonium. This fact has actually been verified in the MSR Experiment of Oak Ridge Lab. Therefore, as far as my understanding goes, since the Thorium Cycle MSR is proliferation resistant, we should be able to buy this technology from the US without any Nuclear deal or any IAEA regime to look over our shoulders. CONCLUSION In the end, I’m afraid, I have to side with the Left in wondering what the urgency was for the Govt. to rush for the Nuclear Deal? As I have tried to highlight the advantages of the Thorium based MSR technology, which is inherently proliferation resistant, my question is: have we really considered all the aspects of the Nuclear technology which are available to us and are we sure that going with the Indo-US Nuclear deal is the only way to secure our future Nuclear Energy options? As I had stated in my earlier post on the Nuclear Deal, “If a deal is too good to be true, it isn’t”. I’m looking for a critical rebuttal of this post. I really need to know, that if the Thorium cycle MSR is proliferation resistant, then why can’t India simply buy this technology from the US WITHOUT going for a Nuclear Deal (and also the Inspection regime of the IAEA)? PS: In my next post I shall frame my response to the terror bomb attacks in the various parts of the country
