Review of Molten Salt Reactor Physics Calculations [Disc 2]
Review of Molten Salt Reactor Physics Calculations [Disc 2]
Review of Molten Salt Reactor Physics Calculations [Disc 2]
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1<br />
REVIEW OF MOLTEN SALT RRACTOR PHYSICS CAUXJLATIONS<br />
1. INTRODUCTION<br />
Q<br />
'<br />
: This review <strong>of</strong> the physics <strong>of</strong> the <strong>Molten</strong>'<strong>Salt</strong> Breeder <strong>Reactor</strong> was<br />
undertaken for the purpose <strong>of</strong> providing an independent,check <strong>of</strong> as'many<br />
aspects as possible <strong>of</strong> the calculations already made. We have not attempted<br />
any further optimization.‘, Instead we chose a design <strong>of</strong> the core<br />
and blanket regions for which calculations had already been made, and<br />
subjected'this design to ouranalysis. Our primary interest *as in the<br />
breeding ratio <strong>of</strong> the equilibrium reactor.<br />
The design we chose is essentially the one presented as the reference<br />
case in OR,NL-~~-1467 (Ref.'l). It is a 1000 Mw(e) power , plant with<br />
a single core, separate fissile and fertile streams, and without provision<br />
for removal <strong>of</strong> 23%a , from the fe rtile stream.<br />
Theprevious calculation for this design is known as Case 555 in a<br />
series <strong>of</strong> calculations by the OPTIMNRC code.' Ins<strong>of</strong>ar as possible we<br />
attempted to specify the same geometry and composition as -case 555,<br />
resisting suggestions that this case is already obsolete, so that a<br />
valid comparison could be made between the two calculations. For 'some<br />
regions,.particularly for the-lower~blanket.Sind plenum,. the' specifications<br />
for case 555 were not detailed enough for our tialculations, or<br />
appeared to leave out 'certain-components. To fill in these gaps we<br />
obtained additional<br />
--<br />
layout drawings and di&ensions from the-group-work-<br />
" -ing'on the design <strong>of</strong> the molten salt reactors.2<br />
Our review covered six principal areas: 'cross sectioi selkction,<br />
fission product treatment, multigroup cell calculaticxls, two-dimensional<br />
~reactor criticality caldulations, equilibrium depletion calculations,<br />
and start up depletion caltiulations. 'In'each area-we attempted to choose<br />
‘methods and data which were as independent as posstble from those used<br />
previously. However, in,a ntiber <strong>of</strong> instances we used the'ssme methods<br />
because al*ernate computer -codes were not-available, a&for many nuclides<br />
we used.essentially the same 'cross-section data because they seemed most<br />
likely<br />
to be correct,