Skip to content
Licensed Unlicensed Requires Authentication Published by De Gruyter (O) May 5, 2020

Influence of plutonyl ion on electrochemical characterization of zirconium in plutonium nitrate solutions

  • Masaumi Nakahara EMAIL logo , Yuichi Sano and Kazunori Nomura
From the journal Radiochimica Acta

Abstract

With the aim of evaluating the corrosion behavior of a Pu evaporator made from Zr in the Rokkasho Reprocessing Plant (RRP), the electrochemical characterization of Zr was investigated in Pu nitrate solutions. Before and after experiments, spectra of Pu nitrate solutions were recorded, and Pu4+ was oxidized to PuO22+ by heating these solutions. The ratio of PuO22+ in 3 mol dm−3 HNO3 was higher than that in 7 mol dm−3 HNO3 in our experiments. The maximum open circuit potential of Zr in the Pu nitrate solution was approximately 1 V in the Pu nitrate solution containing 7 mol dm−3 HNO3. However, there were no significant changes at high PuO22+ concentrations, and this value remained below the passivity breakdown potential under our experimental conditions. In this study, Zr showed high corrosion resistance, even though many PuO22+ ions existed in the Pu nitrate solution containing 7 mol dm−3 HNO3.

References

1. Kiuchi, K.: Corrosion problems and countermeasures to corrosion of reprocessing materials used in boiling nitric acid. J. At. Energy Soc. Jpn. 31, 229 (1989) [in Japanese].10.3327/jaesj.31.229Search in Google Scholar

2. Wada, F.: Improvement of reliability in nuclear fuel reprocessing plant. Zairyo-to-Kankyo 48, 771 (1999) [in Japanese].10.3323/jcorr1991.48.771Search in Google Scholar

3. Ishijima, Y., Kato, C., Motooka, T., Yamamoto, M., Kano, Y., Ebina, T.: Stress corrosion cracking behavior of zirconium in boiling nitric acid solutions at oxide formation potentials. Mater. Trans. 54, 1001 (2013).10.2320/matertrans.M2012341Search in Google Scholar

4. Takeda, S., Nagai, T., Yasu, S., Koizumi, T.: Corrosion performance of several metals in plutonium nitrate solution. Zairyo-to-Kankyo 44, 24 (1995) [in Japanese].10.3323/jcorr1991.44.24Search in Google Scholar

5. Takeda, S., Nagai, T., Koizumi, T.: Corrosion behavior of materials in FBR spent fuel reprocessing solutions. J. At. Energy Soc. Jpn. 36, 146 (1994) [in Japanese].10.3327/jaesj.36.146Search in Google Scholar

6. Nakahara, M., Sano, Y., Abe, H.: Electrochemical properties of zirconium in highly concentrated plutonium nitrate solution. Prog. Nucl. Sci. Technol. 5, 52 (2018).10.15669/pnst.5.52Search in Google Scholar

7. Moore, J. D., Walser, R. L., Fritch, J. J. (Eds.): Purex Technical Manual. RHO-MA-116, Rockwell Hanford Operations, Washington (1980).Search in Google Scholar

8. Lemire, R. J., Fuger, J., Nitsche, H., Potter, P., Rand, M. H., Rydberg, J., Spahiu, K., Sullivan, J. C., Ullman, W. J., Vitorge, P., Wanner, H.: Chemical Thermodynamics of Neptunium and Plutonium, Chemical Thermodynamics Vol. 4, Elsevier, North Holland (2001), pp. 301–316.Search in Google Scholar

9. Committee of Handbook on Process and Chemistry of Nuclear Fuel Reprocessing (Ed.): Handbook on Process and Chemistry of Nuclear Fuel Reprocessing, 3rd Ed., JAEA-Review 2015-002, Japan Atomic Energy Agency, Ibaraki (2015) [in Japanese].Search in Google Scholar

10. The Electrochemical Society of Japan (Ed.): Handbook of Electrochemistry 6th Ed., Maruzen Publishing Co., Ltd., Tokyo (2013), pp. 91−98 [in Japanese].Search in Google Scholar

11. Hagan, P. G., Miner, F. J.: Spectrophotometric Determination of Plutonium III, IV, and VI in Nitric Acid Solutions. RFP-1391, The Dow Chemical Company, Colorado (1969).Search in Google Scholar

12. Glazyrin, S. A., Rodchenko, P. Y., Sokhina, L. P.: Oxidation of plutonium(IV) on heat treatment of concentrated nitrate solutions. Radiokhimiya 31, 48 (1989).Search in Google Scholar

13. Crocker, I. H.: Oxidation of Pu(IV) to Pu(VI) in Solutions of Nitric Acid, Aluminium Nitrate, Sodium Nitrate, and Uranyl Nitrate. CRDC-697, Atomic Energy of Canada Limited, Ontario (1957).Search in Google Scholar

14. Nemoto, S., Koma, Y., Shibata, A., Sakakibara, T., Tanaka, Y.: Np and Pu Co-Recovery in PUREX Process for FBR Spent Fuel. PNC Technical Review No. 99, PNC TNI340 96-003, Power Reactor and Nuclear Fuel Development Corporation, Tokyo (1996), pp. 87–92 [in Japanese].Search in Google Scholar

15. Sato, S., Kudo, K., Kuno, Y., Masui, J.: Effect of temperature on Pu valency with varying Pu concentration and nitric acid concentration. Proceedings of Annual Meeting of Atomic Energy Society of Japan, Kyoto, Japan, March 27−29, 1993, J17 (1993) [in Japanese].Search in Google Scholar

Received: 2019-11-06
Accepted: 2020-04-12
Published Online: 2020-05-05
Published in Print: 2020-09-25

©2020 Walter de Gruyter GmbH, Berlin/Boston

Downloaded on 25.4.2024 from https://www.degruyter.com/document/doi/10.1515/ract-2019-3228/html
Scroll to top button