ORNL-5388 - the Molten Salt Energy Technologies Web Site

i;
1
t
u
1
1
B-3
Table 8.5. Reactor Fuel Fabrication Costsa
Reactor Type
Cost ($/kg HMlb Over First
- Decade After Introductlon
LWR-U5(LE)/U
100 (1969 + 2089)=
LWR-U5( DE)/U/Th
230 (1987) + 140 (1997)
LWR-U3( DE)/U/Th
880 (1991) + 550 (2001)
LWR-PU/U
550 (1991) + 340 (2001)
LWR-PU/Th
550 (1991) + 340 (2001)
SSCR-US( LE)/U
SSCR-U3( DE)/U/Th
SSCR-PU/Th
HWR-U5( NAT)/U
HWR-U5(SEU)/U
HWR-U5( DE)/U/Th
HWR-U3( DE)/U/Th
HWR-PU/U
HWR-PU/Th
HTGR-U5 (LE)/U
HTGR-U5 (DE)/U/Th
HTGR-U5( HE)/Th
C/Th + U = 150
C/Th + U = 238
C/Th + U = 335
C/Th + U = 400
C/Th + U = 650
HTGR-U3( DE)/U/Th
HTGR-U3/Th
C/Th + U = 150
C/Th + U = 238
C/Th + U = 335
C/Th + U = 400..
C/Th + U = 650
100 (1991 * 2089)c
880 (1991) + 550 (2001)
550 (1991) + 340 (2001)
60 (1995 + 2089)c
60 (1995 + 2089)c
140 (1995) + 85 (2005)
560 (1995) + 350 (2005)
320 (1995) + 200 (2005)
320 (1995) + 200 (2005)
340 1995) + 210 (2005)
500 11995) + 300 (2005)
660 (1995) + 400 (2005)
760 (1995) + 470 (2005)
1220 (1995) + 770 (2005)
860 (1995) + 470 (2005)
1220 (1995) + 670 (2005)
1640 (1995) + 900 (2005)
2000 (1995) + 1100 (2005)
3200 (1995) + 1750 (2005)
HTGR-PWTh
C/Th = 238
1220 (1995) + 670 (2005)
FBR-PU-U core
1750 (2001) + 950 (2011)
FBR-Pu-Th core
1750 (2001) -+ 950 (2011)
FBR-U3-U core
3000 (2001) + 1650 (2011)
FBR-U axial blanket 35 (2001) + 25 (2011)
FBR-U radial blanket 250 (2001) + 150 (2011)
FBR-Th axial blanket 35 (2001) + 25 (2011)
FBR-Th radial blanket 250 (2001) + 150 (2011)
'Fabrication costs based on the following: for LWR
and SSCR, a 17 x 17 pin assembly (374-mil-OD pin);
for the HWR, a 37-pin CANDU assembly -20 in. long
(531-mil-OD pin); for the HTGR, standard carboncoated
uranium carbide fissile microspheres formed
into cylindrical rods located in a hexagonal graphite
block; and for the FBR, a 217-pin assembly
in a hexagonal duct (310-mil-00 pin).
bUncertainities on fabrication costs: 235U-bearing
fuels, no uncertainty; Pu-bearing fuels, -10% to
50% increase; 233U-bearing fuels, -10% to 50%
increase.
CCosts assumed to remain constant.
assumed to have been stored, with the
spent fuel stockpile being reduced in an
orderly manner after the advent of reprocessing.
After the spent fuel stockpile
has been reduced to zero, the out-of-reactor
time required for reprocessing and refabrication
is assumed to be two years.
The long-run marginal costs estimated
for U308 ore as a function of the cumulative
supply are shown in Table B-7. As noted in
Chapter 6, the U308 estimates have been
provided by DOE'S Division of Uranium
Resources and Enrichment (URE), the highcost
supply being based on the assumption
that approximately 2.5 million tons of U308
will be available from conventional uranium
ore resources and the intermediate-cost
supply being based on the assumption that
approximately 4.5 million tons of U308
will be available. In either case, it is
assumed that shales can be mined after the
conventional resources are depleted. The
cost of extracting the shales increases
from $125/lb to $240/lb for the high-cost
supply case and from $100/lb to $180/lb
for the intermediate-cost supply case. It
is important to note that the long-run
marginal costs shown in Table B-7 are larger
than the forward costs shown in Table 6.1-1
of Chapter 6 because the long-run marginal
costs contain the capital cost of facilities
currently in operation, plus a normal profit
for the industry. The long-run marginal
costs are more appropriate for use in a
nuclear strategy analysis.
The enrichment costs and tails
compositions assuming e5 ther a continuation
of the gaseous diffusion technology or the
deployment of an advanced enrichment technology
are shown in Table 8-8. It was
assumed that if the gaseous diffusion
technology is continued the tails composition
will be stabilized at 0.0020 and that
the cost of enrichment will increase to
$80/SWU in 1987 and remain constant thereafter.
If an advanced enrichment technology