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Plutonium Biokinetics in Human Body A. Luciani - Kit-Bibliothek - FZK

Plutonium Biokinetics in Human Body A. Luciani - Kit-Bibliothek - FZK

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Uranium-Thorium cycle [5]. For their capacity of produc<strong>in</strong>g fissile materials, 238 U and 232 Th<br />

are therefore called “fertile materials”.<br />

The use of a mixture of fissionable and fertile materials <strong>in</strong> a nuclear reactor can help <strong>in</strong><br />

reduc<strong>in</strong>g the rate of depletion of nuclear fuel, because the excess of neutrons not necessary for<br />

the ma<strong>in</strong>tenance of the fission reaction can be used for convert<strong>in</strong>g the fertile materials <strong>in</strong>to<br />

fissile materials. Thus, for the specific case of Uranium-<strong>Plutonium</strong> cycle, the 235 U can be<br />

burned and the surplus of neutrons produce <strong>Plutonium</strong> 239 Pu from the fertile 238 U. This k<strong>in</strong>d of<br />

nuclear reactor is called converter reactor [6]. The efficiency of this process of production of<br />

new fuel depends on the extent of neutron losses. If these losses are kept small by controll<strong>in</strong>g<br />

and limit<strong>in</strong>g undesirable neutron absorption or neutron leakage, even more fuel can be<br />

produced than that burned. Moreover 239 Pu can be used as a fuel <strong>in</strong> place of the orig<strong>in</strong>al 235 U.<br />

Reactors that burn 239 Pu (or 233 U <strong>in</strong> the Uranium-Thorium cycle) and produce as much, or<br />

more, fuel as is consumed, are called breeder reactors. This k<strong>in</strong>d of reactor is characterized by<br />

a particularly high efficiency <strong>in</strong> breed<strong>in</strong>g Pu by fast neutrons (fast breeder reactors).<br />

In this frame <strong>Plutonium</strong> is first of all and more commonly a by-product of fission<br />

reactions used <strong>in</strong> the nuclear power <strong>in</strong>dustry, because of the ubiquitous presence of 238 U <strong>in</strong><br />

nuclear fuels. <strong>Plutonium</strong> is used only <strong>in</strong> small amounts on its own to fuel reactors, ma<strong>in</strong>ly for<br />

the development of fast breeder reactors. In fact, even if the breeder reactors technology has<br />

given the possibility of us<strong>in</strong>g 239 Pu as fuel, high capital cost, operational difficulties and<br />

doubts over safety have limited the application of this technology, particularly with regard to<br />

the commercially unfavourable process of treatment of spent reactor fuel elements to recover<br />

<strong>Plutonium</strong> [45]. At present <strong>Plutonium</strong> is more commonly used blended with natural or<br />

depleted Uranium <strong>in</strong> so-called mixed-oxide fuels (MOX) for light-water thermal reactors. In<br />

1998 about 20 reactors <strong>in</strong> five countries (Belgium, France, Germany, Japan and Switzerland)<br />

were loaded with MOX fuel, but the number is expected to rise <strong>in</strong> the next years because the<br />

use of MOX fuels reduces the <strong>in</strong>ventory of separated <strong>Plutonium</strong>, thereby reduc<strong>in</strong>g the<br />

problems of safe <strong>Plutonium</strong> storage, even if extensive handl<strong>in</strong>g of <strong>Plutonium</strong> is still<br />

necessary. However the multiple recycl<strong>in</strong>g <strong>in</strong> light-water reactors degrades <strong>Plutonium</strong>,<br />

limit<strong>in</strong>g the number of times it can be recycled to two or three [46]. After such use and<br />

without the possible follow<strong>in</strong>g application of <strong>Plutonium</strong> as fuel for fast breeder reactors, spent<br />

MOX fuel ends up <strong>in</strong> a f<strong>in</strong>al depository or <strong>in</strong> storage facilities.<br />

Beside the civilian applications, <strong>Plutonium</strong> was extensively used for military purposes<br />

for manufactur<strong>in</strong>g nuclear explosives. An explosive fission reaction can be generated with<br />

<strong>Plutonium</strong> by two different procedures: Br<strong>in</strong>g<strong>in</strong>g together rapidly two chunks of fissile<br />

material, each with subcritical mass, to achieve a supercritical mass (“gun” technique) or<br />

compress<strong>in</strong>g a sphere of <strong>Plutonium</strong> by application of concentrated high explosives (implosion<br />

technique) [47]. The <strong>Plutonium</strong> used <strong>in</strong> nuclear warheads is produced with dedicated<br />

production reactors. The spent fuel from power reactors conta<strong>in</strong>s a large amount of 238 U, and<br />

some 235 U, 239 Pu, 240 Pu and 241 Pu. If this “reactor grade” <strong>Plutonium</strong> is chemically separated and<br />

made <strong>in</strong>to a weapon, the presence of neutrons from the spontaneous fission of 240 Pu will cause<br />

premature detonation and an <strong>in</strong>efficient explosion. Therefore specific reactors were designed<br />

and operated to produce “weapon grade” <strong>Plutonium</strong> with high concentration of the fissile<br />

239 Pu and lower concentrations of the other isotopes, notably 240 Pu. Usually the <strong>Plutonium</strong> for<br />

military purposes conta<strong>in</strong>s less than seven per cent of 240 Pu.<br />

The nuclear power production <strong>in</strong> the civilian area and the weapons manufacture <strong>in</strong> the<br />

military sector are the ma<strong>in</strong> applications of <strong>Plutonium</strong> and consequently the ma<strong>in</strong> sources of<br />

<strong>in</strong>ventoried <strong>Plutonium</strong>. Estimates for <strong>in</strong>ventories of <strong>Plutonium</strong> at the end of 1990 <strong>in</strong> these two<br />

fields of application are shown <strong>in</strong> Table 1.2.2 [modified from 48]. Of the total <strong>in</strong>ventoried<br />

<strong>Plutonium</strong> (911 tons), 72 % comes from civilian <strong>in</strong>ventories (654 tons) and of this 83 % is<br />

15

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