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neptunium can be stored as an oxide; however, safeguards control is necessary,<br />

since it is in principle a fissile material.<br />

Conditioning of separated neptunium for long term storage can be<br />

achieved by transforming it into, for example, a Synroc type of compound (a<br />

mixture of zirconolite, hollandite and perowskite), which is much more<br />

insoluble than glass forms. Long term surface storage or retrievable disposal in<br />

underground facilities are options to be studied.<br />

Target fabrication for future transmutation is another alternative. For<br />

example, mixing of NpO 2 with aluminium powder and transformation into<br />

uranium/plutonium/neptunium subassemblies makes it suitable for irradiation<br />

in thermal and fast neutron flux reactors or in ADS facilities.<br />

Irradiation by thermal neutrons [9] produces large inventories of 238 Pu,<br />

while irradiation in FRs or in fast spectrum ADSs reduces this formation but<br />

does not eliminate it. Multiple recycling in dedicated FR or ADS facilities has<br />

to be considered to achieve complete incineration. Hot refabrication of 237 Np–<br />

238 Pu targets is a technology that needs development in order to ensure a high<br />

decontamination factor (DF) from the ingrown actinides ( 239 Pu, 240 Pu).<br />

The following industrial facilities and processes will be necessary to<br />

produce and process the irradiation targets resulting from a reactor system of<br />

100 GW(e) [1]:<br />

(a)<br />

(b)<br />

(c)<br />

(d)<br />

(e)<br />

(f)<br />

(g)<br />

A neptunium chemical purification plant with a capacity of ~1.6 t/a;<br />

A neptunium target fabrication facility of an equivalent capacity;<br />

Interim safeguarded (or underground retrievable) storage of fresh<br />

neptunium targets;<br />

A dedicated chemical processing rig for irradiated targets;<br />

A hot refabrication plant for recycling of 237 Np– 238 Pu targets;<br />

An HLW connection with an LWR UO 2 vitrification plant;<br />

A medium level alpha waste treatment plant for effluent processing.<br />

Long term storage or disposal of ~1.6 t of 238 Pu and fission products (880<br />

and 190 kW(th), respectively) will be necessary, depending on the fission rate<br />

and the cooling period.<br />

A dedicated FR or ADS transmutation facility should be erected in the<br />

immediate vicinity. This complex ought to be associated with one of the big<br />

industrial reprocessing plants, in order to avoid unnecessary transfers and<br />

transport on public roads.<br />

The real benefit of this development for waste management is the<br />

reduction of the neptunium inventory and of the very long term radiological<br />

risk associated with the migration of 237 Np into the biosphere. However, it has<br />

to be remembered that quantitative transmutation of industrial quantities of<br />

17

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