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6.2. DISCUSSION OF RESULTS FOR SELECTED
NUCLEAR POLICY OPTIONS
This section discusses results obtained in this study for a selected set of nuclear
system options that typify the role of nuclear power under different nuclear policy deci-
sions. The intent is to identify the basic issues, to determine the logical consequences
of decisions made in accordance with those issues, and to display the consequences in an
illustrative manner.
Section 6.1 are presented in Appendix C.
Detailed results for all the nuclear system options outlined in
6.2.1. The Throwaway/Stowaway Option
The throwaway/stowaway cycle (see Fig. 6.1-1) is a conceptually simple nuclear system
option and therefore has been selected as the reference cycle against which all other op-
Avg. Capacity Factor = 0.67
Tails Ccmmosition - 0.W20
-
r n
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m
-
HTGR
Fig. 6.2-1. Lifetime U308 Requirements
for Various Reactors on the Throwaway Cycle.
-1
tions are compared.
ly understand the implications of the throw-
away cycle, the effect of several deployment
options utilizing the various advanced con-
verters on the throwaway cycle was analyzed
in detail. In general, the analysis assumed
a nuclear growth rate of 350 GWe in the year
2000 followed by a net increase of 15 GWelyr,
but the consequences of a significant reduc-
tion in the nuclear growth rate were also
considered. In addition, the effect of both
the high-cost and the intermediate-cost
U308 supplies was determined.
In order to thorough-
A summary of the 30-yr U308 requirements
for several reactors on the throwaway cycle,
including an LWR with a fuel system designed
for an extended discharge exposure, is
shown in Fig. 6.2.1. In each case, the
average capacity factor of the reactor was
assumed to be 0.67, and the tails composi-
tion of the enrichment plant was assumed to be 0.0020. As the figure indicates, all the
reactors have lower U308 requirements than the standard LWR, the extended-discharge LWR being
6% lower, the SSCR 16% lower, the HTGR 23% lower, and the slightly enriched HWR 39% lower.
These U308 requirements were calculated for essentially standard designs without elaborate.
design optimization.
performance characteristics; however, the goal of this analysis was not to delineate the
ultimate role of any particular reactor concept based on current performance characteristics,
but rather to identify the probable role of each reactor concept and the incentive for
improving its performance characteristics.
It i s recognized that design optimization could improve the reactor