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Nuclear Science and Technology: On the Determination of the Pu 240 in Solid Waste Containers by Spontaneous Fission Neutron Measurements Application to Reprocessing Plant Waste.

UNSPECIFIED (1975) Nuclear Science and Technology: On the Determination of the Pu 240 in Solid Waste Containers by Spontaneous Fission Neutron Measurements Application to Reprocessing Plant Waste. [EU Commission - Working Document]

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    Item Type: EU Commission - Working Document
    Subjects for non-EU documents: UNSPECIFIED
    Subjects for EU documents: Energy Policy > Nuclear
    Energy Policy > Nuclear & Nuclear Safety/Radiation Protection
    Research and Technology Policy > Joint Research Centre
    Research and Technology Policy > Nuclear/Fusion
    EU Series and Periodicals: RTD:Nuclear Science and Technology
    EU Annual Reports: UNSPECIFIED
    Institutional Author: European Communities, July 1967 to October 1993 > Commission
    Depositing User: Phil Wilkin
    Official EU Document: Yes
    Language: English
    Date Deposited: 02 Jan 2020 19:19
    Number of Pages: 58
    Last Modified: 02 Jan 2020 19:19
    URI: http://aei.pitt.edu/id/eprint/94563

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