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7.3. PROSPECTS FOR IMPLEMENTATION AND COMMERCIALIZATION
OF DENATURED 233U FUEL CYCLE
J. C. Cleveland and T. J. Burns
Oak Ridge National Laboratory
Chapter 5 has discussed the reactors in which denatured 23% might be deployed, as
we1 1 as the accompanying fuel recycle facility requirements , and has presented schedules
of d ployment that are based solely on the minimum time estimated to be required to solve
technical problems.
evaluations presented in Chapter 6, were developed in discussions between Hanford Engi-
neering Development Laboratory (HEDL) Argonne National Laboratory (ANL) , Oak Ridge
National Laboratory (ORNL)
specifically as a bounding case for assessing the maximum benefits that could be obtained
by employing denatured 23% fuel. As a result, the schedules are not entirely consistent
with those that have been developed subsequently in the Nonproliferation A1 ternative
Systems Assessment Program (NASAP). While the introduction dates of the lead plants do
not differ significantly, the NASAP scenarios predict a much slower deployment of
commercial reactors.
These schedules, which have been used in the nuclear power system
Combustion Engineering (CE) , and the Department of Energy (DOE)
The reactor introduction dates and deployment schedules used in this study were
based on the following assumptions:
~ 1 yr 0 to develop/commercialize new fuel design
%14 yr to develop/comercialize modified reactor design
~ 1 yr 8 to develop/commercialize new advanced converter design
.~24 yr to develop/commercialize new breeder design
The resulting introduction dates for the various reactors are as listed below, where the
introduction date is defined as the date of startup of the first unit, reactor deployment
thereafter being limited to a maximum introduction rate*' by biennium of 1, 2, 4, . reactors:
1969 - LWRs operating on LEU fuel
1987 - LWRs operating on "denatured 235U'' fuel (i.e., MEU(235)/Th)
1991 - LWRs operating on denatured 233U, Pu/U, and Pu/Th fuels
1991 - SSCRs operating on LEU, denatured 233U, or Pu/Th fuels
1995 - HWRs operating on any of several proposed fuels
1995 - HTGRs operating on any of several proposed fuels
2001 - FBRs operating on PUN, Pu/Th, or denatured 233U fuels
Since the above introduction dates are those estimated to be the earliest possible
dates that technical problems could be resolved, it is clear that they cannot be achieved
without substantial initiatives and strong financial support from the U.S., Government.
*
The introduction rate of any new technology is likely to be less than the maximum rate
noted above, since the construction market loss rate of an established technology is
limited to 10% per year and total nuclear capacity additions cannot exceed 15 GWelyr.
233U systems are further constrained because the number or 233U-burning plants that can
be operated is limited by the 23%1 production rate.