Long-Term Chemical Alteration of 238Pu-Doped Borosilicate Glass in a Simulated Geological Environment with Bentonite Buffer

Author:

Zubekhina Bella1,Burakov Boris2ORCID,Shiryaev Andrei3ORCID,Liu Xiaodong4,Petrov Yury5

Affiliation:

1. Japan Atomic Energy Agency, 2-4 Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan

2. The Ioffe Institute, 26 Politekhnicheskaya St., St. Petersburg 194021, Russia

3. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Leninsky Pr., 31 korp. 4, Moscow 119071, Russia

4. State Key Laboratory of Nuclear Resources and Environment, East China University of Technology, 418 Guanglan Ave, Nanchang 330013, China

5. Khlopin Radium Institute, 28 2-nd Murinskiy Ave., St. Petersburg 194021, Russia

Abstract

Chemical degradation of borosilicate glass doped with 238Pu was modelled in conditions of a failed underground radwaste repository in granite host rock with bentonite buffer material after penetration of aqueous solutions at temperature of 90 °C. The total duration of the experiment exceeded two years. It is shown that wet bentonite preserved its barrier function and prevents migration of plutonium to the solution. The total amount of plutonium adsorbed on bentonite clay during the experiment did not exceed 0.02% of the initial amount of plutonium in the glass sample. Estimated accumulated dose of self-irradiation of the glass sample after the experiment varies from 3.16 × 1015 to 3.39 × 1015 α-decays per gram, which is equivalent to more than 1000 years storage of 239Pu doped sample with the same Pu content. Beishan granite remained intact, with no evidence of Pu penetration into the granite matrix along mineral grain boundaries.

Publisher

MDPI AG

Subject

Management, Monitoring, Policy and Law,Renewable Energy, Sustainability and the Environment,Geography, Planning and Development,Building and Construction

Reference33 articles.

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3. Ojovan, M.I., Petrov, V.A., and Yudintsev, S.V. (2021). Glass Crystalline Materials as Advanced Nuclear Wasteforms. Sustainability, 13.

4. International Atomic Energy Agency (2013). Characterization of Swelling Clays as Components of the Engineered Barrier System for Geological Repositories, IAEA. IAEA-TECDOC-1718.

5. Effects of deposited nuclear and electronic energy on the hardness of R7T7-type containment glass;Peuget;Nucl. Instrum. Methods Phys. Res.,2006

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