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The proliferation potential of neptunium, though being significantly inferior to the one of plutonium, has been recognized by the IAEA. As neptunium has not been attributed, the status of special nuclear material, the established system of quantitative accountancy and verification does not apply. A flow-sheet verification (FSV) scheme has been proposed, to verify that neptunium is not separated during nuclear fuel reprocessing.

In the present paper, we illuminate the build-up of neptunium under different reactor scenarios, covering commercial reactors like pressurized water reactor (PWR), CANDU or RBMK, but also gas-cooled reactors and MTR. Criteria for the identification of a useful ôtracerö will be discussed. FSV makes use of the concept of measuring Np relative to a fission product, which serves as reference. Finally, analytical methods-existing or to be adapted-will be examined for their applicability in this context. .

Additional information

Authors: MAYER K, EC-JRC, Institute for Transuranium Elements (ITU), Karlsruhe (DE);PEERANI P, EC-JRC, Institute for Transuranium Elements (ITU), Karlsruhe (DE)
Bibliographic Reference: An oral report given at: 23rd. ESARDA Annual Meeting of Safeguards and Nuclear Material Management. Held at: Bruges, (BE) 8-10 May (2001)
Record Number: 200013754 / Last updated on: 2001-09-18
Original language: en
Available languages: en
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