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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5-8<br />
<strong>the</strong> LMFBR on its reference cycle are currently being revised, and a study of L.e denatured<br />
fast breeder fuel cycle, which includes fast transmuters and denatured breeders, is included<br />
as part of <strong>the</strong> INFCE program (International Nuclear Fuel Cycle Evaluation).<br />
from <strong>the</strong> INFCE study should be available in <strong>the</strong> near future.<br />
5.1.1. Light-Water Reactors<br />
The results<br />
Preliminary evaluations of design and safety-related considerations for LWRs operat-<br />
ing on <strong>the</strong> conventional thorium cycle indicate thorium-based fuels can be employed in LWRs<br />
with little or no modification.<br />
Consequently, <strong>the</strong> R&D costs given here have been estimated<br />
under <strong>the</strong> assumption that denatured fuel will be employed in LWRs of essentially present<br />
design. This assumption is not meant to exclude minor changes to reactor design (for<br />
example, changes in <strong>the</strong> number of control drives, shim loadings, or fuel management, etc.)<br />
but ra<strong>the</strong>r reflects our current belief that design changes necessitated by DUTH fuels will<br />
be sufficiently straightforward so as to be accommodated within <strong>the</strong> engineering design<br />
typically performed for new plants.<br />
As has been described in <strong>the</strong> discussion above, <strong>the</strong> first phase of such fuel-cyclerelated<br />
research consists of <strong>the</strong> development of a data base from which safety-related<br />
parameters and fuel performance can be predicted in subsequent core physics design and<br />
safety analysis programs. First, existing thorium materials and fuel performance information<br />
should be thoroughly reviewed, and a preliminary evaluation of safety and licensing<br />
issues should be made in order to identify missing information and guide <strong>the</strong> subsequent<br />
development program. Although this initial phase is required to fully define <strong>the</strong> required<br />
data base R&D, it is possible to anticipate in advance <strong>the</strong> need to establish information<br />
in <strong>the</strong> areas of physics verification and safety-related fuel performance.<br />
As shown in Table 5.1-1, <strong>the</strong> physics verification program under data base development<br />
is estimated to cost %$lo million. This program should be designed both to provide<br />
<strong>the</strong> information required to predict important safety-related physics parameters and to<br />
demonstrate <strong>the</strong> accuracy of such predictions as part of <strong>the</strong> safety analysis. Improved<br />
values must be obtained for cross sections of thorium and of isotopes in <strong>the</strong> thorium<br />
depletion chains, such as 233U and protactinium, all of which have been largely neglected<br />
in <strong>the</strong> past. Resonance integral measurements should also be performed for denatured fuels<br />
both at room temperature and at elevated temperatures, such experiments being very important<br />
for accurately calculating safety-related physics characteristics and also for<br />
establishing <strong>the</strong> quanti ties of plutonium produced during irradiation. Finally, an LWR<br />
physics verification program should include a series of critical experiments, preferably<br />
both at room temperature and at elevated moderator temperatures, for each of <strong>the</strong> fuel<br />
types under consideration (i .e. , for thorium-based fuels utilizing denatured 23sU, denatured<br />
233U, or plutonium). These experiments would serve as a basis for demonstrating <strong>the</strong> adequacy<br />
of <strong>the</strong> cross-section data sets and of <strong>the</strong> ability of analytical models to predict such<br />
safety-related parameters as reactivity, power distributions, moderator temperature<br />
reactivity coefficients, boron worth, and control rod worth.