Development of Solubility Improvement Technology for Nitric Acid of Plutonium Dioxide in Scrap MOX Powder-Reference-Cited by-同舟云学术

Development of Solubility Improvement Technology for Nitric Acid of Plutonium Dioxide in Scrap MOX Powder

Published:2015 Issue:2 Volume:14 Page:75-85
ISSN:1347-2879
Container-title:Transactions of the Atomic Energy Society of Japan
language:en
Short-container-title:Transactions of the Atomic Energy Society of Japan

Author:

KATO Yoshiyuki¹

Affiliation:

1. Tokai Reprocessing Center, Nuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency

Publisher

Atomic Energy Society of Japan

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference15 articles.

1. 1) A. L. Uriarte, R. H. Rainey, Dissolution of High Density UO₂, PuO₂, and UO₂-PuO₂ Pellets in Inorganic Acids, ORNL-3695 (1965).

2. 2) D. Vollath, H. Wedemeyer et al., “On the dissolution of (U, Pu) O₂ solid solutions with different plutonium contents in boiling nitric acid,” Nucl. Technol., 71, 240-245 (1982).

3. 3) S. Sakurai, S. Tachimori, J. Akatsu, T. Kimura, Z. Yoshida, H. Mutoh, T. Yamashita, K. Ohuchi, “Dissolution of plutonium dioxide by electrolytic oxidation method, (I) Determination of dissolution conditions and preliminary test for scaling-up,” Nihon-Genshiryoku-Gakkai Shi (Trans. At. Energy Soc. Jpn.), 31[11], 1243-1250 (1989), [in Japanese].

4. 4) M. Umeda, M. Nakazaki, T. Kida et al., Characteristics of MOX Dissolution with Silver Mediated Electrolytic Oxidation Method, JAERI-Tech, 2003-024 (2003), [in Japanese].

5. 5) Development section, Conversion technology development division, Tokai works, “Design and tests of wet recovery equipment using solvent extraction by pulsed column,” PNC Tech. Rev., 59, 50-55 (1986), [in Japanese].