MSR Benefits

Molten Salt Reactor Advantages

  • Molten Fuel - Fuel circulates through the reactor, fission products get removed, for over 99% fuel use (vs. LWR ~3%). No long-term radioactive waste.
  • Salt Cooled - Coolant far below boiling point, reactor operates at atmospheric pressure. Fuel dissolved in stable salt (no water), no loss of coolant accident possible. No need for high-pressure safety systems.
  • High Inherent Safety - No water, no high pressure, nothing that could propel radioactive materials into the environment. Thermal expansion/contraction of molten fuel salt strongly regulates fission rate; MSR is a very stable reactor. Simple safety systems work even if no electricity or operators.
  • Easy Construction and Siting - Low pressure operation, so no high-pressure safety systems. No water, so no steam containment building. Reactor factory assembled, with modern quality control, sensors and communication.
  • Lower Cost - Even with exotic materials, construction costs will be dramatically lower than LWR — factory construction, minimal manual on-site preparation. No long-term radioactive waste, so no long-term storage.
  • High Temperature Operation - Heat to generate electricity, desalinate water, produce CO2-neutral vehicle fuel, etc.
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With molten fuel, a LFTR would generate 4,000 times less mining waste and up to 10,000 times less nuclear waste than any solid fueled reactor. The fission byproducts can be easily extracted, so the fuel can fission completely.

Solid-fueled Light Water Reactor, to make 1 gigawatt-year electricity need 250 tons uranium (incl 1.75 tons U-235), make 35t enriched uranium (1.15t U-235). Leaves 215t depleted uranium (0.6t U-235), 35t spent fuel (33.4t U-238, 0.3t U-235, 1.0t fission products, 0.3t plutonium). Kirk Sorensen TEAC3

Molten Salt Reactors (e.g. LFTR) to make 1 gigawatt-year electricity: need 600 to 800 kg (0.8 ton) of Thorium or any isotope of Uranium. D. LeBlanc / Nuclear Engineering and Design 240 (2010)

The uranium (or plutonium or other transuranic elements) are completely fissioned in a MSR. (Thermal or epithermal spectrum MSR can fission U233, U235, Pu239; fast spectrum MSR can fission all isotopes of uranium and transuranic elements. All MSR can breed Th to U233 or U238 to Pu239.) 83% of the waste (fission byproducts) from a LFTR are safely stabilized within 10 years. The remaining 17% (135kg for a GigaWatt-year) are elements that need to be stored less than 350 years to become completely benign. 135kg vs 250 tons (250,000kg) from a LWR.

A 40-megawatt test reactor running for 10 years would “burn” 141 Kg. U-233, and produce less than 1 milligram of plutonium or other transuranic elements. Leave these inside the reactor, where neutron bombardment will cause them to fission. Charles Holden, TEAC 2011

from Kirk Sorensen’s presentation slides TEAC3

The traditional “waste problem” includes storing all the uranium with the fission byproducts. However, separating the uranium (and plutonium) is easy; we don’t because of the “reprocessing is bad” conversations, but storing uranium in low density so chain reaction is impossible is simple and produces low levels of radiation. Many fission byproducts are very short-lived (half lives in seconds to months), and therefore highly radioactive.

As the separated fission products have much smaller volume, they can be left as salts and allowed to solidify and decay in short-term storage. (Other storage can work, in vitrified glass, for example.)

“FS-MSRs can be employed to consume actinides from light-water reactor (LWR) fuel or, alternatively, to extend fissile resource availability through uranium-to-plutonium breeding. FS-MSR reactors are highly flexible and can be configured into modified open or full-recycle configuration. The modified open FS-MSR fuel cycle options do not include chemical processing of the fuel salt. … The conversion ratio of an FS-MSR is largely determined by the fissile-to-fertile-material ratio in its fuel salt. Thus, a single reactor core design may be capable of performing both fissile resource extension and waste disposition missions.”
Fast Spectrum Molten Salt Reactor Options, Oak Ridge National Laboratory, July 2011

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