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FOREWORD<br />

Almost all States with a nuclear power capability consider geological<br />

disposal as the end point for spent fuel declared as waste and also for the long<br />

lived radionuclides and high level waste resulting from the reprocessing of<br />

spent fuel. However, several States are considering or investigating partitioning<br />

and transmutation (P&T) as a potential complementary route in the<br />

management of the radioactive material resulting from nuclear power<br />

generation.<br />

P&T has the potential to open new avenues for long term waste<br />

management and to reduce the radiological hazard (in terms of magnitude and<br />

duration), to weaken the decay heat evolution history (e.g. by eliminating long<br />

lived heat producing actinides) and to reduce the quantities of the fissile and/or<br />

fertile radionuclides that pose proliferation concerns.<br />

Whereas only the major nuclear power States are potentially capable of<br />

developing a self-supported P&T activity, States with more modest<br />

programmes are studying the impact of P&T on their own waste management<br />

programmes and strategies.<br />

Recognizing this, and taking into account the increased interest in<br />

advanced and innovative nuclear fuel cycles and reactor systems, the IAEA<br />

initiated in 2001 a programme dedicated to preparing a report analysing the<br />

current status of P&T. Potential options for implementing P&T and its<br />

potential impact on waste management programmes and strategies were<br />

evaluated from an international perspective.<br />

The first draft report was prepared at a meeting from 15 to 19 October<br />

2001 by four consultants: L.H. Baetslé (Belgium), M. Embid-Segura (Spain),<br />

J. Magill (Germany) and N. Rabotnov (Russian Federation). A status report on<br />

the subject was prepared by L.H. Baetslé. During a Technical Committee<br />

Meeting (TCM) held in September 2002, a draft document was discussed,<br />

revised and substantially extended by ten participants and representatives of<br />

the IAEA Departments of Safeguards and Nuclear Safety. After this meeting,<br />

the report was finalized at a meeting from 7 to 11 April 2003 by the same group<br />

of consultants, also including L. Stewart from the USA.<br />

The IAEA wishes to express its appreciation to all those who took part in<br />

the preparation of this report. Particular acknowledgement is due to L.H.<br />

Baetslé, who chaired the TCM and put great effort into the completion and<br />

technical polishing of the report.<br />

The IAEA officer responsible for this report was R. Burcl of the Division<br />

of Nuclear Fuel Cycle and Waste Technology.

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