ORNL-5388 - the Molten Salt Energy Technologies Web Site

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for later recycle could be initiated by the mid-1980's if such incentives
were forthcoming. Recycle of 233U on a commercial scale is not plausible
prior to the year 2000, however.
The introduction of advanced reactor concepts that would provide significant
resource savings beyond the year 2000 will require very large government
support for R&D, for demonstration facilities, and for lead comnercial
plants. If a rapid deployment schedule were required, additional resources
would have to be committed to cover the risks of early commercial plants.
Fuel service/energy centers whose ultimate purpose is to utilize plutonium both
for energy production and for 233U production would progress through various
phases. Initially these centers would be fuel storage facilities. With the
introduction of reprocessing and retabrication in the center, LWRs located at
dispersed sites would be fueled with denatured 233U. Concurrently Pu-fueled
thermal transmuters would be deployed within the center. Ultimately, to meet
long-term energy demands, Pu-fueled fast transmuters would be introduced
within the centers.
It is desirable that a fuel recycle R&D program be initiated for denatured fuels
at the same time a decision is made to fabricate thorium-containing fuel
for large-scale irradiation in existing LWRs. Pilot-scale recycle facilities
could be required within seven years after the initiation of a thorium
irradiation program.
Section 7.3 References
N. L. Shapiro, J. R. Rec, R. A. Matzie (Combustion Engineering), "Assessment of
Fuel Cycles in Pressurized Water Reactors," EPRI-NP-359 (February 1977).
"Assessment of Utilization of Thorium in BWRs," ORNL/SUB-4380/5 (NEDG-24073),
prepared by General Electric Company (January 1978).
"The Economics and Uti1 ization of Thorium in Nuclear Reactors,'' ORNL-TM-6331
(also Technical Annexes 1 and 2, ORNL-TM-6332) prepared by Resource Planning
Associates, Inc. (May 1978).
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