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Thorium Reactor

  1. Sep 2, 2005 #1
  2. jcsd
  3. Sep 3, 2005 #2
    Significance of thorium-232/uranium-233 breeder reactor

    Breeding thorium-232 to obtain fissile uranium-233 is significant for India because, as Richard Garwin has pointed out, India has more access to thorium than it does to uranium.

    For the rest of the world, thorium represents and important nuclear fuel resource in combination with uranium resources (land-based thorium resources are four times as high as land-based uranium resources) and is one of the reasons humans are not likely to need to breed plutonium from uranium-238 for fuel within the next 10,000 years.
  4. Sep 3, 2005 #3


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    For those interested in the technical aspects.

    ATBR - A Thorium Breeder Reactor Concept for Early Induction of Thorium in an Enriched Uranium Reactor

    V. Jagannathan, Usha Pal, R. Karthikeyan, S. Ganesan, R. P. Jain, S. U. Kamat

    Volume 133 · Number 1 · January 2001 · Pages 1-32
    Technical Paper · Fission Reactors

    Abstract - A new reactor concept has been proposed for induction of thorium in an enriched uranium reactor. The neutronic characteristics of the fissile and fertile materials have been exploited to arrive at optimal fuel assembly and core configurations. Each fuel assembly consists of an enriched uranium seed zone and a thoria blanket zone. They are in the form of ring-type fuel clusters. The fuel is contained in vertical pressure tubes placed in a hexagonal lattice array in a D2O moderator. Boiling H2O coolant is used. The 235U enrichment is ~5.4%. The thoria rods contain the 233U bred in situ by irradiation of one batch load of mere thoria clusters (without the seed zone) for one fuel cycle in the same reactor. There is no need for external feed enrichment in thoria rods. Additionally, some moveable thoria clusters are used for the purpose of xenon override. The fissile production rate from the fertile material and the consumption rate of fissile inventory is judiciously balanced by the choice of U/Th fuel rod diameter and the number and location of thoria rods in the fuel assembly and in the core. During steady-state operation at rated power level, there is no need for any conventional control maneuvers such as change in soluble boron concentration or control rod movement as a function of burnup. Burnable poison rods are also not required. A very small reactivity fluctuation of ±2 mk in 300 effective full-power days of operation is achieved and can be nearly met by coolant inlet enthalpy changes or moveable thoria clusters. Control is required only for cold shutdown of the reactor. The uranium as well as thoria rods achieve a fairly high burnup of 30 to 35 GWd/tonne at the time of discharge. Since the excess reactivity for hot-full-power operation is nearly zero at all times during the fuel cycle and since the coefficients of reactivity due to temperature and density variations of coolant are nearly zero by design, there is hardly any possibility of severe accidents involving large reactivity excursions.

    Thorium fuel has had limited experience in the US as part of demonstration programs in the Shippingport and Indian Point 1 reactors, which have been shutdown for sometime.

    See also - Thorium, UIC Nuclear Issues Briefing Paper # 67, November 2004
    Last edited: Sep 3, 2005
  5. Sep 5, 2005 #4
    Thanx for the abstract..
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