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    Please use this identifier to cite or link to this item: http://ir.lib.ncu.edu.tw/handle/987654321/78060

    Title: 107年用過核子燃料處置安全審驗及平行驗證技術建立;Development of Long-term Safety Evaluation and Verification Techniques for Disposal of Spent Nuclear Fuel
    Authors: 黃偉慶;王韡蒨;張瑞宏;鐘志忠
    Contributors: 國立中央大學土木工程學系
    Keywords: 深層地質處置;用過核子燃料;審驗技術;deep geological disposal;spent nuclear fuel;verification technique
    Date: 2018-12-19
    Issue Date: 2018-12-20 10:54:08 (UTC+8)
    Publisher: 行政院原子能委員會
    Abstract: 參酌用過核燃料最終處置先進國家國際審查經驗,「107年用過核子燃料處置安全審驗及平行驗證技術建立」之研究內容中,國際高放最終處置計畫安全分析報告、安全評估報告資訊研析部分,將以日本原子力發電環境整備機構(NUMO)於2013年所發表的「地質處置計畫安全性2010」摘要報告為主要研析標的,輔以2016年NEA對日本高放射性廢棄物地質處置選址程序的國際審查報告。 日本原子能委員會(JAEC)所屬政策評估委員會於2008年提出,NUMO應針對能安全實施高放地質處置發表報告證明其技術可行性,且此報告將經由外部且獨立的學術機構審查,以便修正,同時也應反映最新的相關知識進行定期更新。「地質處置計畫安全性2010」報告即在此背景下發表,內容可分為計畫實施(project implementation)與技術(technologies)兩個主要部分,其中計畫實施章節係提出確保地質處置計畫安全實施的政策,而技術章節則提出科學知識發展的進展及支持地質處置安全概念的技術,以及實施處置計畫的準備狀態。本研究即針對日本高放射性廢棄物地質處置計畫安全性報告,掌握其計畫實施與技術章節內容加以研析。同時,將應用104年至今對國際高放處置安全評估資訊研析的成果,對國內台電公司2017年底所提出「用過核子燃料最終處置技術可行性評估報告」(SNFD 2017),進行關鍵議題研析與長期安全評估驗證工作,並提出評析結果與建議。 另一方面,針對用過核子燃料處置安全分析所需的重要管制資訊及技術,將以國際間普遍重視且已進行國際合作計畫的課題為目標,進行資訊蒐集與成果平行驗證,包括處置設施溫度參數、間隙及開挖擾動帶效應分析及平行驗證技術建立、工程障壁緩衝材料潛變及處置環境模型實驗技術驗證、以及處置設施低鹼性混凝土性質審驗技術及其與周邊環境作用機制資訊研析等。 ;This project aims at referencing the international reviewing experiences on the safety report of geological repository for spent nuclear fuel in nuclear-advanced countries. The focus of this year’s review will be on the “Safety of the Geological Disposal Project 2010” published by NUMO in 2013. In addition, the review report prepared by NEA on Japan’s siting process for the geological disposal of high-level radioactive wastes will also be studied. The NUMO 2010 Technical Report is comprised of 2 main parts. The project implementation chapters present the policies for ensuring the safe implementation of the geological disposal project; while the technologies chapters present the progress made through development of scientific knowledge and the technologies that support the safety concepts for the geological disposal. As Taipower has submitted ite report on “Technical Feasibility Evaluation on the Final Disposal of Spent Nuclear Fuel” at the end of 2017, the findings from this and past studies will be used to evaluate the preparation of the siting process and technical feasibility of the geological disposal in Taiwan. In addition to the build-up of reviewing capacities of the FCMA, some verifications on the technical features of the safety report are also of importance in the build-up of reviewing capabilities. Hence, three more technical sub-studies, namely, near-field temperature field, gap and disturbance effects and their confirmation, creep behavior of buffer material and near-field scenario simulation and verification, and properties of low pH cement concrete and its interactions with the surroundings in a repository, are included in this research project.
    Relation: 財團法人國家實驗研究院科技政策研究與資訊中心
    Appears in Collections:[土木工程學系 ] 研究計畫

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