• Title/Summary/Keyword: Nuclear waste

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Validation of Radioanalytical Techniques for Nuclear Waste Characterisation

  • Warwick, Phillip E.
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.4
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    • pp.363-373
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    • 2019

  • Waste characterisation associated with nuclear site decommissioning relies on radiochemical analysis of a diverse range of sample types, requiring extensive validation of analytical techniques using matrix-matched materials. The absence of relevant reference materials has hindered robust method development and validation. The paper discusses how method validation in support of nuclear waste characterisation can be achieved without using reference materials. The key stages in an analytical procedure are evaluated and a multi-stage approach is proposed with the ultimate aim of determining an operational envelope for an analytical procedure.

  • https://doi.org/10.7733/jnfcwt.2019.17.4.363 인용 PDF KSCI

WOLSONG LOW- AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE DISPOSAL CENTER: PROGRESS AND CHALLENGES

  • Park, Jin-Beak;Jung, Hae-Ryong;Lee, Eun-Young;Kim, Chang-Lak;Kim, Geon-Young;Kim, Kyung-Su;Koh, Yong-Kwon;Park, Kyung-Woo;Cheong, Jae-Hak;Jeong, Chan-Woo;Choi, Jong-Soo;Kim, Kyung-Deok
    • Nuclear Engineering and Technology
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    • v.41 no.4
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    • pp.477-492
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    • 2009

  • In this paper, we discuss the experiences during the preparation of the Wolsong Low- and Intermediate-Level Radioactive Waste Disposal Center. These experiences have importance as a first implementation for the national LILW disposal facility in the Republic of Korea. As for the progress, it relates to the area of selected disposal site, the disposal site characteristics, waste characteristics of the disposal facility, safety assessment, and licensing process. During these experiences, we also discuss the necessity for new organization and change for a radioactive waste management system. Further effort for the safe management of radioactive waste needs to be pursued.

  • https://doi.org/10.5516/NET.2009.41.4.477 인용 PDF KSCI

Preliminary Analysis on Decommissioning Strategies for Fukushima Daiichi Nuclear Power Station From Waste Management Perspective

  • Watanabe, Naoko;Yanagihara, Satoshi
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.19 no.3
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    • pp.297-306
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    • 2021

  • In this study, basic strategies for the decommissioning and site remediation of the Fukushima Daiichi Nuclear Power Station (FDNPS) were investigated. Six scenarios were formulated based on two of the three decommissioning strategies of nuclear power plants defined by the International Atomic Energy Agency (IAEA): immediate dismantling and deferred dismantling. A multicriteria decision analysis was performed to analyze the preferences of the options from the viewpoints of the timeframe to complete decommissioning, the resulting waste, the site usability, and the availability of the radioactive waste disposal route. The same six scenarios were applied to both the FDNPS and the nuclear power plants that ceased operation after a normal plant life cycle for comparison. For the FDNPS, the decommissioning project involved fuel debris retrieval, dismantling, and site remediation. The analysis results suggest that the balance between the amount of waste and the time to achieve the end state may be one of the most critical factors to consider when planning the decommissioning and site remediation of the FDNPS.

  • https://doi.org/10.7733/jnfcwt.2021.19.3.297 인용 PDF KSCI

Studies on the Physico-chemical Properties of Mixed Radioactive Waste Glass

  • Kim, C.W.;Choi, J.R.;Ji, P.K.;Park, J.K.;Shin, S.W.;Ha, J.H.;Song, M.J.;Hwang, T.W.;Park, S.J.
    • Journal of Radiation Protection and Research
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    • v.29 no.1
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    • pp.33-39
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    • 2004

  • In order to vitrify the W1 waste (ion-exchange resin(IER), zeolite, and dry active waste(DAW)) generated from Korean Nuclear Power Plants, a glass formulation development based on waste compositions and production rates was performed. A aluminoborosilicate glass, AG8W1, was formulated to vitrify the W1 waste in an induction cold crucible melter(CCM). The processability, product performance, and economics of the candidate glass were calculated using a computer code and were measured experimentally in the laboratory and CCM. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. Start-up and maintaining glass melt of the candidate glass were favorable in the CCM. The product quality of the glass such as chemical durability, phase stability, etc. was satisfactory. The vitrification process using the candidate glass was also evaluated to be operated as economically as possible.

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