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ORNL-5388 - the Molten Salt Energy Technologies Web Site

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3.18<br />

There are three approaches which can be employed to estimate allowable enrichnent<br />

criteria for 233U in 238U corresponding to <strong>the</strong> statutory 20% limit set for 235U in 238U.<br />

These three criteria are: (1) critical mass, (2) infinite multiplication factor, and<br />

(3) yield.<br />

Critical Mass<br />

These can be employed singularly or in combination as discussed below.<br />

As stated above, <strong>the</strong> bare-sphere critical mass of metallic 20% 235U and 80% 238U is<br />

about 850 kg. This amount can be reduced by a factor of two to three by <strong>the</strong> use of a<br />

neutron reflector.<br />

fissile material will not be substantially less than that of <strong>the</strong> bare sphere, and may<br />

even be greater. In addition, for a nuclear explosive, an assembly scheme must be added<br />

which will increase <strong>the</strong> size and weight substantially. Concentrations of 235U, 233U, or<br />

plutonium in mixtures with 238U such that <strong>the</strong>y have bare-sphere metallic critical masses<br />

of about 850 kg represent one possible reasonably conservative criterion for arriving at<br />

concentrations below which <strong>the</strong> material is not usable in practical nuclear weapons. This<br />

850 kg bare-sphere critical mass criterion can also be used for o<strong>the</strong>r materials which are<br />

or might be in nuclear fuel cycles. Although this criterion provides a basis for consistent<br />

safeguards requirements for 233U or 235U embedded in 238U, it leans to ra<strong>the</strong>r<br />

low limits.<br />

Infinite Mu1 tip1 ication Factor<br />

However, <strong>the</strong> size and weight of <strong>the</strong> combination of reflector and<br />

ho<strong>the</strong>r possible criterion is <strong>the</strong> one associated with <strong>the</strong> infinite multiplication<br />

factor k,. For a weapon to be successful, a certain degree of supercriticality must be<br />

attained. D. P. Smith of Los Alamos Scientific Laboratory has adopted this approach. He<br />

takes k, = 1.658 for 20% 235U-enriched uranium, which implies k, = 1.5346 for <strong>the</strong> oxide.<br />

He <strong>the</strong>n performs a search calculation on enrichment for <strong>the</strong> o<strong>the</strong>r systems so as to obtain<br />

<strong>the</strong> same k, value. His results are shown in Table 3.3-1. We note that for 233U <strong>the</strong> limits<br />

are 11.65% 233U for <strong>the</strong> oxide and 11.12% 233U for <strong>the</strong> metal.<br />

Fuel<br />

Table 3.3-1 Equivalent Enrichment Limits<br />

Hateri a1 kco<br />

Metal 20% 235U, 80% 238U 1.658<br />

11.12% 233U, 88.88% 238U 1.658<br />

11.11% 239Pu, 88.89% 238U 1.658<br />

Oxide (20% 235U, 80% 238U)02 1 5346<br />

(11.65% 233U, 88.35% 238U)02 1.5346<br />

(13.76% 239P~, 86.24% 238U)02 1.5346<br />

(14.5% 239Pu, 1.5% 240Pu, 85% 238u)02 1.5344<br />

~ ~ ~~~ ~~~ ~<br />

These numbers were obtained by D. P. Smith of Los Alamos<br />

Scientific Laboratory from DTF IV calculations using<br />

Hansen-Roach cross sections.

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