Suggested research topics for molten salt reactors

The following is a partial list of research topics that could have a substantial improvement in the prospects for a commercially viable product.

  • Thermostat negative temperature control. The point of this topic is to end up with a strong negative temperature coefficient even at high temperatures and with low fission product burden.
    1. neutron poison rods are actuated by temperature response
    2. need to develop a design that is compatible chemically and good for neutron economy and for waste management

  • All carbon composite primary system. The point of this research idea is to be able to operate at high enough temperature (~900°C) for a direct cycle gas turbine or (~1050°C) to make hydrogen by thermo chemical water splitting cycle. We are speaking of vessel, piping, pumps and heat exchangers.
    1. allows higher temperature
    2. avoid corrosion of metal alloys
    3. better tritium control with SiC layer
    4. can SiC be used to improve the neutron damage characteristics of graphite? The problem is thermal stresses and de-bonding due to differential thermal expansion

  • Alternative salt formulations. The point of this research is to avoid the problems listed below with Li and Be.
    1. Li results in tritium production and lithium-7 is expensive
    2. Be is expensive and hazardous to work with due to inhalation toxicity. Look at NaF, ZrF4, look at solubility enhancement, corrosion, neutron loss.

  • Safeguard and non proliferation analyses in use of Th-U-233 cycle. The point of this topic is to understand proliferation issues.
    1. make most or all of fuel once started up (CR~1)
    2. maybe start up on reactor minor actinides (Pu and higher); get credit for taking on this material rather than paying for enriched U
    3. enhance U-232 production to promote non-proliferation by making diversion of U-233 harder, less desirable and easier to detect. See item 9 below.

  • Centrifuge for noble and semi-noble metal separations. The point of this work is to improve the outlook for extraction and handling of the precipitating fission products to enhance waste management strategies.
    1. base on continuous flow contactor
    2. incorporate into pump

  • Waste form and assay study. This topic emphasizes waste management, a vital aspect of nuclear energy.
    1. estimate assay (carry over of actinides) with each class of waste, e.g., gaseous, noble and semi-noble metals and valence two and three products with reductive extraction. Consider Bi carry over and resulting Po-210.
    2. waste form: fluoride for interim and substitute fluorapatite for permanent storage

  • Plant description, size, undergrounding, cost, systems. Economic considerations are important motivators to develop this new nuclear power system.
    1. change out time for graphite vs. core size
    2. salt formulation
    3. underground design considerations
    4. cost analysis preliminaries
    5. power conversion cycle

  • System assessment along lines of NERI-2002 proposal. What is known about the molten salt reactor is decades old. Bringing up to date the database is vital to resurrecting the molten salt reactor development.

  • U232 proliferation for thorium
  • Kang and von Hipple article
  • J.D. Lee et al. UCID 19327 (1982)
    1. part 1, 429 pages
    2. part 2, 398 pages
    3. chapter VII, 92 pages, on proliferation/fuel cycles by Dave Berwald, with special emphasis on the role of Pa231/U232.


    Suggested research topics

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    Last updated August 4, 2009.