ORNL-5388 - the Molten Salt Energy Technologies Web Site
ORNL-5388 - the Molten Salt Energy Technologies Web Site
ORNL-5388 - the Molten Salt Energy Technologies Web Site
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Table 4.2-1. Fuel Utilization Characteristic2 for SSCRs<br />
Under Various Fuel Cycle Optionsa*<br />
Initial<br />
Equilibrium Cycle<br />
Fissile Fissile 30-Yr Cumulative<br />
30-Yr Cumulative<br />
Separative Work<br />
Fuel Type<br />
Fissl le Inventory<br />
(kg/GWe 1<br />
Makeup<br />
(kg/GWe-yr)<br />
Discharge<br />
(kg/GWe-yr)<br />
U30, Requirement<br />
(ST/GWe)<br />
Requirement'<br />
(lo3 kg SW/GWe)<br />
Dispersible Resource-Based Fuels<br />
LEU, no recycle 1577 23511 713 235U 182 23%<br />
196 Puf<br />
MEU/Th. 23sU feed, 2540<br />
U recycle<br />
371 2ssU 228 235U<br />
371 233U<br />
65 Puf<br />
Dispersible Denatured Fuel<br />
Denatured 233U02/Th02, 1663 233U 236 233U<br />
U recycle<br />
PuO2/ThOz, Pu recycle 2354 Puf<br />
4; E;<br />
72 Puf<br />
<strong>Energy</strong>-Center-Constrained Fuel<br />
791 Puf 780<br />
273<br />
Puf<br />
233U<br />
3 235u<br />
5320 3010<br />
3220 3077<br />
--<br />
--<br />
-- --<br />
'1290-MWe SSCR; IO-MWe additional power required to run reactor coolant pumps and 020 upgrader facility.<br />
bAs~umes 75% capacity factor, annual refueling, and 0.2 w/o tails assay.<br />
mode of operation. Because <strong>the</strong> basic PWR NSSS* is used, <strong>the</strong> utilization of <strong>the</strong> denatured<br />
thorium fuel cycles will pose no additional problems or R&D needs beyond those required<br />
to implement this type of fuel in <strong>the</strong> conventional PWR. Although <strong>the</strong> general feasibility<br />
of spectral-shift control appears relatively well established, never<strong>the</strong>less <strong>the</strong>re are a<br />
number of aspects of SSCR design which must be evaluated in order to fully assess <strong>the</strong><br />
conercial practicality of spectral-shift-controlled reactors. The more significant of<br />
<strong>the</strong>se are briefly discussed below.<br />
1. Resource Utilization - A more accurate assessment of resource utilization is<br />
required to more definitively establish <strong>the</strong> economic incentives for spectral-shift control<br />
on <strong>the</strong> LEU cycle.<br />
water reactors, <strong>the</strong> savings in Uj08 and separative work for 235U-based systems must be<br />
demonstrated to be sufficiently large to compensate for <strong>the</strong> additional capital cost of<br />
equipment required to implement spectral-shift control. A similar assessment for<br />
denatured 233U fuel is also required.<br />
If <strong>the</strong> concept is to be economically competitive with conventional<br />
2. Plant Modifications - The plant modifications necessary to realize spectral-<br />
shift control must be identified, and <strong>the</strong> cost of <strong>the</strong>se modifications established, The<br />
practicality and cost of <strong>the</strong>se modifications, of course, bear directly on <strong>the</strong> economics<br />
and commercial feasibility of <strong>the</strong> concept. Of particular concern are modifications which<br />
may be required to limit <strong>the</strong> leakage of primary coolant (from valve stems, seals, etc.)<br />
and <strong>the</strong> equipment required to recover unavoidable primary coolant leakage. Primary<br />
coolant leakage is important both from <strong>the</strong> standpoint of economics, because of <strong>the</strong> high<br />
cost of D20, and from <strong>the</strong> standpoint of radiation hazard, because of <strong>the</strong> problem of occu-<br />
pational exposures to tritium during routine maintenance, O<strong>the</strong>r possible modifications to<br />
current'designs which result from <strong>the</strong> presence of D20, such as <strong>the</strong> increased fast fluence<br />
on <strong>the</strong> reactor vessel and possible changes in pumping power, will also have to be addressed.<br />
NSSS = Nuclear Steam supply 'System.