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MSR: Molten Salt Reactor System

Physics Monday, May 7, 2007 . This is a SciScoop post by DV82XL

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 In the MSR reactor fission occurs in a circulating molten salt fuel mixture in a neutron stingy reactor that permits a full actinide burn fuel cycle. In the MSR system, the fuel, a circulating liquid mixture of sodium, zirconium and uranium fluorides, flows through graphite core channels in the reactor chamber where it undergoes fission. The hot molten salt is then continuously pumped through a secondary coolant system, through an intermediate heat exchanger, and then through a tertiary heat exchanger where energy is extracted. MSR’s operate at high temperatures. They typically employ salts with melting points in excess of 650C. This means that the core containment vessel and heat exchangers must be made of high-temperature materials (such as nickel alloys). While the salt is continually circulating, fusion only occurs in the reactor proper in the presence of the graphite moderator. Molten fluoride salts have excellent heat transfer characteristics and a very low vapour pressure, which reduces stress on the vessel and plumbing.

The MSR’s liquid condition allows the direct addition of fuel as required and avoids the need for fuel fabrication. The MSR can be operated as a breeder reactor on a 232Th-233U fuel cycle that generates a waste with almost no long-lived actinides. The closed fuel cycle can be tailored to the efficient burnup of plutonium and minor actinides. Actinides and most fission products form fluorides in the liquid coolant. MSR’s also have the flexibility to utilise any fissile fuel mix in continuous operation with no special modification of the core.

One of the features of the MSR is that the fuel must undergo on-line reprocessing. The on-line reprocessing is necessary to keep the reactor in operation, clearing away typical reactor poisons like xenon and krypton. Also when operating as a breeder protactinium is produced as well, unfortunately, 233Pa has a moderately large absorption cross section and a half-life of 27 days. If it is left in the reactor, parasitic capture of neutrons by 233Pa will occur, resulting in a significant reduction in the breeding ratio.  To avoid this, on-line processing must also remove the 233Pa and store outside of the reactor until it decays to 233U.

The characteristics of the MSR also offer the potential for large economics of scale in very large reactors compared to other designs, yet it can also be produced in a low volume design, in fact the first of this type was developed to power aircraft, although this never came to fruition. Like any nuclear reactor, thorium reactors will be hot and radioactive, necessitating shielding. The amount of radioactivity scales with the size of the plant. It so happens that thorium itself is an excellent radiation shield, but lead and depleted uranium are also suitable.

More information can be found at these pages of the excellent website, Energy from Thorium:

Introduction and Basic Principles

Introducing the Liquid-Fluoride Reactor

A Brief History of the Liquid-Fluoride Reactor

2 Responses to MSR: Molten Salt Reactor System

Crusty

May 13th, 2007 at 9:18 pm

This looks like a typical lobby-influenced rehash of an old proposed type of reactor. In fact sodium-cooled reactor have been tried for decades and never worked properly in large installations. The sodium is far too corrosive for long-term use in  today’s metal piping and will eat through it in years. At the same time it reacts explosively (literally!) with any water in the vicinity. So any leak from primary to secondary cooling system, which are known to happen, will tear the reactor apart.

At the same time, proposing using uranium salts into the sodium itself (as opposed to in zirconiumsteel confines in the reactor vat itself as is normal) is seriously complex. This is known to the authors of  above articles, otherwise they wouldn’t be worth their salt. In industrial installations, complexity equals tons of money.

Thirdly, on-line processing of this type of reactor is clearly dangerous, difficult and very, very costly. This is not a CanDu reactor. They are proposing to filter inpurities from the primary coolant while in use. Normally, used-up uranium rods are placed in swimming-pool sized baths filled with water to cool down. Did I mention that when molten sodium is placed in water it explodes?
On-line processing means adding as much new doped coolant as is removed, otherwise al sorts of bad things can happen. Did I mention Murphy’s law?
Difficult, dangerous, and very expensive.

Fourth, there is currently no such type of reactor working on this planet. Expect to toss in at least 15 years and at least 10 Billion Dollar into this money pit before it becomes remotely workable. By that time both wind and geothermal will be insanely more cheaper than this monstrosity.

So, like the nuclear industry always does, this is simply a warming up to plea for government subsidies. Hey, it worked for them before…

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DV82XL

May 15th, 2007 at 9:12 am

To start off with these are not sodium-cooled fast breeder reactors – they are an entirely different technology. Second two of them have been successfully built and operated in the 1950’s. Thirdly sodium cooling loops have been tested at length by AECL for periods measured in years without any corrosion issues. Fourthly, this type of reactor does not need to use liquid-metal cooling at all, and the reaction takes place in halide salts which are relatively neutral to nickel-based alloys thus no sodium needs to come in contact with water.

Off-line reprocessing largely consists of holding the material at sub-critical mass while the Pa decays into U and electro winning the other transactinides out on anodes.

I would strongly suggest that you read the links posted in the article to gain a deeper understanding of this reactor before commenting further as you don’t seem to have a very good grasp of the principles involved.      

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