[en] A new EC plutonium reference material is made available in the form of 5g samples of plutonium dioxide powder. Before weighing the material must be calcined at 1 250⁰C for two hours. The plutonium content (880.26 ± 0.44) g.kg^-1 has been derived from plutonium measurements performed by three different laboratories each applying a different oxydo-reductive method. The results of the plutonium measurement, the statistical evaluation of the uncertainty of the plutonium content together with information on the impurities present in the material are given in the report

[en] The main objective of this research is to evaluate health-risk distributions for plutonium (Pu) inhalation-exposure scenarios relevant to environmental management of plutonium dioxide (PuO2)-contaminated sites. These distributions incorporate variability/uncertainty

[en] The packaging has been developed as a packaging for plutonium oxide to be recovered from light water reactor spent fuel and is designed for easy handling within a facility. As deformation and shock absorption data for balsa wood, the data obtained from various experiments carried out when developing the packaging were used. With this packaging, it is possible to transport almost all kinds of raw powder materials required to produce fuel as stated under Section 2 not only in the country but also from abroad. The packaging is expected to be frequently used in transporting plutonium oxide powder from England and/or France which are commissioned by domestic power companies to reprocess spent fuel and also in transporting highly enriched uranium oxide which is required at FBR experimental reactors. 14 references, 5 figures, 4 tables

No abstract available

No abstract available

[en] An Addendum was written to the Model 9977 Safety Analysis Report for Packaging adding a new content consisting of DOE-STD-3013 stabilized plutonium dioxide materials to the authorized Model 9977 contents. The new Plutonium Oxide Content (PuO₂) Envelope will support the Department of Energy shipment of materials between Los Alamos National Laboratory and Savannah River Site facilities. The new content extended the current content envelope boundaries for radioactive material mass and for decay heat load and required a revision to the 9977 Certificate of Compliance prior to shipment. The Addendum documented how the new contents/configurations do not compromise the safety basis presented in the 9977 SARP Revision 2. The changes from the certified package baseline and the changes to the package required to safely transport this material is discussed

[en] Several studies have been undertaken in France in this area. For the program discussed here, an experimental prototype facility was set up at the CEA's Cadarache Nuclear Research Center. This unit was designed for filling and emptying large-capacity (25 kg) containers, and for connecting and disconnecting them with industrial facilities without the use of vinyl wrappers. This paper describes the facility and discusses its operating principles before presenting some of the significant results obtained during active testing

[en] Three plutonium metals whose impurity contents have been accurately determined are used to evaluate spectrographic standards. Best results are obtained when (1) highly impure samples are diluted, (2) the internal standard, cobalt, is used, (3) a linear curve is fitted to the standard data that bracket the impurity concentration, and (4) plutonium standards containing 22 impurities are used

No abstract available

No abstract available