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ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site

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94<br />

A major feature of <strong>the</strong> DMSR is <strong>the</strong> relative unavailabil2ty of special<br />

nuclear material (SM) that might be diverted and converted into strategic<br />

special nuclear material (S%NM) for use in <strong>the</strong> production of nuclear ex-<br />

plosive devices.<br />

<strong>the</strong>re would never be any subunits (e8gos fuel elements) that would be par-<br />

ticularly enriched in a given "desirable" material or depleted with re-<br />

spect to specific contaminants. IR addition, because <strong>the</strong> initial fuel<br />

charge as well as all makeup fuel would be denatured 235U and because<br />

"spentr8 fuel would not be XXTIIO'T~~ .from <strong>the</strong> primary co~~taiment except dur-<br />

ing decommissioning at <strong>the</strong> end of reactor life, <strong>the</strong> accessibility sf even<br />

<strong>the</strong> mixed fueh would be severely restricted. Postulating ways of obtain-<br />

ing SSM from any mixture containing fissile nuclides is always possible,<br />

but, in <strong>the</strong> case of <strong>the</strong> DMSR, <strong>the</strong>se appear to involve special difficulties<br />

as well low prsauctivity,<br />

Because all <strong>the</strong> fuel would be in a bonogeneous fluid,<br />

3.7.1 Potential sources of SSMM<br />

Mter <strong>the</strong> first few years of power operation," <strong>the</strong> principal fissile<br />

nuclide in a DMSR would be 233U with<br />

substantial amount of 235U. HOW-<br />

ever, both nuclides would remain fully denatured during <strong>the</strong> entire opera-<br />

tion. Thus s af ter diversion alad Separation from o<strong>the</strong>r CkaelD?Cd. speC%@s<br />

(many of which would be highly radioactive), <strong>the</strong> fissile uranium would<br />

still have to be subjected to an isotope enrichment process to produce<br />

SSNM. o<strong>the</strong>r isotopic contaminants in <strong>the</strong> uranium, notably 232~s would<br />

tend to make tklis a difficult approach.<br />

Tne next m~st abundant fissile material in DMSR fuel salt would be<br />

plutonim, w$th a maximum t~tal-plant fnventory (at end of plant life) of<br />

334 kg of 239Pu -k 241Pu. However, this material would also contain 182 kg<br />

of 242h and 1.39 kg of 240~u, which wuid tend to detract from its value<br />

*<br />

Initially, <strong>the</strong> dominant fissile nuclei would be 23'~ denatured<br />

with 238~, but because this mixture presumably would be an item of international<br />

comerce, <strong>the</strong> DMSR would not represent a particularly attractive<br />

source of supply.

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