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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,

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