Bulletin of the Chinese Ceramic Society, Volume. 42, Issue 8, 2781(2023)

High Temperature Melting Treatment of Simulated Structural Concrete Nuclear Waste

LIU Chunyu1,*... YUAN Yukun1, LI Lili1, FANG Guang2 and XU Kai2 |Show fewer author(s)
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  • 1[in Chinese]
  • 2[in Chinese]
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    References(6)

    [10] [10] OJOVAN M I. Handbook of advanced radioactive waste conditioning technologies[M]. Cambridge, UK: Woodhead Pub, 2011.

    [11] [11] OJOVAN M I, LEE W E. Introduction to immobilisation[M]//An Introduction to Nuclear Waste Immobilisation. Amsterdam: Elsevier, 2005: 1-8.

    [12] [12] Standard test methods for determining chemical durability of nuclear, hazardous, and mixed waste glasses and multiphase glass ceramics: the product consistency test (PCT): ASTM C1285—14[S]. ASTM International, 2014.

    [13] [13] WANG Z F, LIU C Y, FANG G, et al. Vitrification of nuclear contaminated lead-boron polyethylene[J]. Journal of Non-Crystalline Solids, 2021, 564: 120832.

    [14] [14] NIU C C, ZHAO C, ZHOU X, et al. Immobilization of technetium-99 in a lead borosilicate glass[J]. Journal of Non-Crystalline Solids, 2023, 603: 122110.

    [15] [15] VIENNA J, KIM D, HRMA P. Database and interim glass property models for Hanford HLW and LAW glasses[R]. PNNL-14060, Pacific Northwest National Laboratory, Richland, WA, 2002.

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    LIU Chunyu, YUAN Yukun, LI Lili, FANG Guang, XU Kai. High Temperature Melting Treatment of Simulated Structural Concrete Nuclear Waste[J]. Bulletin of the Chinese Ceramic Society, 2023, 42(8): 2781

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    Paper Information

    Category:

    Received: Mar. 18, 2023

    Accepted: --

    Published Online: Nov. 1, 2023

    The Author Email: Chunyu LIU (liuchunyu@cgnpc.com.cn)

    DOI:

    CSTR:32186.14.

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