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A stable solid spike for the measurement of uranium and plutonium content in nitric acid solutions of spent nuclear fuel by isotope dilution mass spectrometry has been prepared at the European Commission Institute for Reference Materials and Measurements in Belgium. The spike contains about 50 mg of uranium with a 19.838% $^{235}$ U enrichment and 2 mg of plutonium with a 97.766% $^{239}$ Pu abundance in each individual ampoule. The dried materials were covered with a thin film of cellulose acetate butyrate as a protective organic stabilizer to resist shocks encountered during transportation and to eliminate flaking-off during long-term storage. It was found that the cellulose acetate butyrate has good characteristics, maintaining a thin film for a long time, but readily dissolving on heating with nitric acid solution. The solid spike containing cellulose acetate butyrate was certified as reference material IRMM-1027f with certified quantities: $^{235}$ U and $^{239}$ Pu amounts and uranium and plutonium amount ratios, and was validated by analyzing spent fuel dissolver solutions of the Tokai reprocessing plant in Japan.

Oral presentation

Joint validation of the in-situ uranium age dating method

Okubo, Ayako; Mayer, K.*

no journal, ,

Under the collaboration between EC-JRC and JAEA, the in-situ age dating method was subject to joint validation, and six different uranium materialswere used for this purpose. The age dating result by in-situ isotope method was consistent with known production dates of the respective samples. The uncertainty evaluation according to GUM for the in-situ isotope method indicates that the measured $^{234}$ Th/ $^{230}$ Th ratio provides the highest contribution. The accuracy of in-situ isotope method can be improved by higher precision in $^{234}$ Th/ $^{230}$ Th measurement.

Oral presentation

Development of an active neutron NDA apparatus for nuclear non-proliferation and nuclear security, 7-3; Measurements with the Prompt Gamma-ray Analysis (PGA) part

Furutaka, Kazuyoshi; Ozu, Akira; Toh, Yosuke

no journal, ,

no abstracts in English

Oral presentation

Development of active neutron NDA system for nuclear non-proliferation and nuclear security, 7-4; Measurements with the Neutron Resonance Transmission Analysis (NRTA) part

Tsuchiya, Harufumi; Kitatani, Fumito; Toh, Yosuke

no journal, ,

no abstracts in English

Oral presentation

Development of active neutron NDA system for nuclear non-proliferation and nuclear security, 7-1; Project overview

Toh, Yosuke; Tsuchiya, Harufumi; Ozu, Akira; Furutaka, Kazuyoshi; Kitatani, Fumito; Komeda, Masao; Maeda, Makoto; Koizumi, Mitsuo

no journal, ,

no abstracts in English

Presentation/Publication Type

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Development of an integrated active neutron non-destructive analysis system; Active-N

The Design and implementation of the PGA measurement system in an integrated Active Neutron non-destructive analysis system, "Active-N"

Development of active non-destructive analysis technologies for nuclear nonproliferation and security of JAEA

Development of neutron resonance densitometry as a technique of material accountancy of nuclear materials with complicated shapes and components; Development of a technique of nuclear material measurements in particle like debris

Preparation, certification and validation of a stable solid spike of uranium and plutonium coated with a cellulose derivative for the measurement of uranium and plutonium content in dissolved nuclear fuel by isotope dilution mass spectrometry

Joint validation of the in-situ uranium age dating method

Development of an active neutron NDA apparatus for nuclear non-proliferation and nuclear security, 7-3; Measurements with the Prompt Gamma-ray Analysis (PGA) part

Development of active neutron NDA system for nuclear non-proliferation and nuclear security, 7-4; Measurements with the Neutron Resonance Transmission Analysis (NRTA) part

Development of active neutron NDA system for nuclear non-proliferation and nuclear security, 7-1; Project overview