Thorium fuel cycle performance

The quantities of uranium and thorium shown in the flow sheet Fig. 3.33 have been adapted from a study by Pigford [P2] of the fuel-cycle performance of the HTGR after a sufficient number of cycles have been operated to permit buildup of steady-state amounts of recycle and diluent In earlier cycles the amounts of these two isotopes are lower. 

The use of the thorium-uranium fuel cycle in the HTGR provides improved core performance over the plutonium/uranium low-enrichment... 

To achieve a fuel management scheme with the lowest fuel cycle cost consistent with the current thermal and material performance limits, the following parameters are selected (l)a fuel cycle incorporating uranium/thorium (2) a fuel lifetime of four years (3) an average power density of 8.4 W/cm3 and (4) a refueling frequency of once a year. 

GA is currently performing parametric studies on the LEU/Th (dual particle) fuel cycle in hopes of utilizing the thorium breeding to significantly expand the fuel cycle length while requiring less fuel ore. 

There is thus no single fuel-cycle strategy that is optimal for all countries at all times. So, in parallel with the development of specific fuel cycles and advanced HWR fuel designs is the development of generic advancements in fuel design and performance that can be applied to any of these advanced fuels, including SEU, MOX, or thorium, or to natural uranium. These include the following ... 

The performance targets for thoria fuel will depend on the specific fuel cycle that is intended. The requirements for a low burnup, near-breeder type of cycle will be different from those to be met by high bumup thorium fuel. 

The fuel cycle using thorium based on A. Radkowsky s RTR (Radkowsky Thorium Reactor) concept [VII-4], which has been studied in the RRC Kurchatov Institute for some years, is considered the prospective development of the VBER-300 to increase cost efficiency, enhance safety and protection of the environment. As a result of investigations performed by the RRC Kurchatov Institute , the concept of the VVER-T reactor has been developed, making maximum use of the existing WER-1000 technology, equipment and engineering solutions [VII-5], This concept is also supposed to be usable in the VBER-300. 

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