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Radiological impacts of spent nuclear fuel management options (2000)

Author	NEA
Date	2000
Classification	6.01.5.50/72 (WASTE - RADIOACTIVE WASTE GENERAL)
Front

FOREWORD

This comparative study on the radiological impacts of spent nuclear fuel management
options was launched by the OECD Nuclear Energy Agency (NEA) at the request of
the OSPAR Commission in 1995. The main objectives of the study were to compile
the most recent data and information on radioactive releases from the different stages
of two selected nuclear fuel cycles (with and without reprocessing), to analyse
radiological impacts in a systematic manner, to interpret the results from the
scientific and technological standpoint, and to contribute to informed discussions
in NEA Member countries. The study was carried out by the Ad Hoc Expert Group
on Spent Fuel Management Options under the NEA Committee on Radiation
Protection and Public Health. The Expert Group held five meetings between
October 1997 and September 1999.

Two simplified reference fuel cycles (with and without reprocessing) based on
pressurised-water reactors (PWR) were selected to facilitate the comparison of
radiological impacts. Actual data on radioactive releases from reference facilities
were used. Reference facilities were selected considering their scale, technological
characteristics, duration of operation, characteristics of the installed waste
management process, as well as regulatory requirements. Radiological impacts
were evaluated with generic models and complemented with results of studies
carried out by national and international organisations.

As some operations in the nuclear fuel cycle are still in the process of development,
some uncertainties remain. These operations include the reprocessing of mixed-
oxide fuel (MOX), the conditioning of spent uranium and MOX fuel for disposal,
and the geological disposal of spent fuel and vitrified high-level waste. Given that
situation and to the extent that the two reference fuel cycles chosen have several
stages in common, efforts were made to apply common assumptions in order to
reduce uncertainties.

The study is intended to be generic and limited in scope. While radiological
impacts, which are the focus of this study, are important for the decision-making
process, it should be noted that certain elements excluded from this study (e.g.,
resource utilisation efficiency, energy security, economic considerations) should
also be considered when making fuel cycle choices.

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