Preparation of Microvolume Anion-Exchange Cartridge for Inductively Coupled Plasma Mass Spectrometry-Based Determination of 237Np Content in Spent Nuclear Fuel-Reference-Cited by-同舟云学术

Preparation of Microvolume Anion-Exchange Cartridge for Inductively Coupled Plasma Mass Spectrometry-Based Determination of 237Np Content in Spent Nuclear Fuel

Published:2016-02-25 Issue:6 Volume:88 Page:3149-3155
ISSN:0003-2700
Container-title:Analytical Chemistry
language:en
Short-container-title:Anal. Chem.

Author:

Asai Shiho¹,Hanzawa Yukiko¹,Konda Miki¹,Suzuki Daisuke¹,Magara Masaaki¹,Kimura Takaumi¹,Ishihara Ryo²,Saito Kyoichi²,Yamada Shinsuke³,Hirota Hideyuki³

Affiliation:

1. Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Ibaraki 319-1195, Japan

2. Department of Applied Chemistry and Biotechnology, Chiba University, Inage, Chiba 263-8522, Japan

3. INOAC Corporation, Atsuta, Nagoya 456-0054, Japan

Publisher

American Chemical Society (ACS)

Subject

Analytical Chemistry

Link

https://pubs.acs.org/doi/pdf/10.1021/acs.analchem.5b04330

Reference28 articles.

1. Okumura, K.; Okamoto, T.Nuclide Inventories of Spent Fuels from Light Water Reactors, JAEA-Data/Code 2011-020, Japan Atomic Energy Agency, February 2012.

2. Improved radioanalytical method for the simultaneous determination of Th, U, Np, Pu and Am(Cm) on a single TRU column by alpha spectrometry and ICP-MS

3. Determination of237Np in spent fuel by use of inherent239Np as a chemical yield monitor

4. Sequential separation of americium, curium, plutonium, neptunium and uranium in various matrices from the electrometallurgic treatment of spent-nuclear fuel

5. Chemical and Isotopic Characteristics of a Neptunium Sample for Nuclear Data Measurements

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