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    Please use this identifier to cite or link to this item: http://ir.lib.ncu.edu.tw/handle/987654321/81963


    Title: 108年用過核子燃料處置審驗技術研析及驗證工作;Study on the Safety Assessment Reviewing and Task Verification for Final Disposal of Spent Nuclear Fuel
    Authors: 黃偉慶;王韡蒨;張瑞宏;楊樹榮
    Contributors: 國立中央大學土木工程學系
    Keywords: 用過核子燃料;深層地質處置;審驗技術;spent nuclear fuel;deep geological disposal;verification technique
    Date: 2020-01-13
    Issue Date: 2020-01-13 14:00:24 (UTC+8)
    Publisher: 行政院原子能委員會
    Abstract: 台電公司於2017年底提出「我國用過核子燃料最終處置技術可行性評估報告」(SNFD 2017),先後經過國際同儕及國內主管機關的審查,為我國用過核子燃料最終處置計畫中重要之階段性安全分析報告。該報告係以瑞典核燃料及廢棄物管理公司(SKB)所提出之最終處置概念KBS-3為基礎,採用過核子燃料直接處置方式,且處置母岩以花崗岩為主要考量,輔以我國K區參考案例,說明台電公司現階段處置工程設計概念之掌握能力,以利於後續逐步推動安全處置作業。 基於上述,本計畫擬針對瑞典輻射安全管制局(Swedish Radiation Safety Authority, SSM)對SKB於2011年所提SR-Site計畫Forsmark處置場執照申請案發表之審查成果,即主審查階段(Main review phase)的30冊審查報告,分別就場址特性、處置設施、安全評估、輻射安全與法規等方面進行研析,俾利於掌握處置計畫推動方向及審查技術發展要項。同時,針對用過核子燃料處置安全評估所需的重要管制資訊及技術,以SNFD 2017報告內容或國際上普遍重視且已進行國際合作計畫的課題為標的,進行資訊蒐集與成果之平行驗證,包括處置設施母岩空間異質性分析驗證及處置罐圍壓分析平行驗證、緩衝材料與回填材料之熱-水-力耦合參數實驗及近場長期變位模式驗證、以及應用於高放處置設施之低鹼性混凝土配比及其性質研析等。 ;Taipower completed a report on “Technical Feasibility Evaluation on the Final Disposal of Spent Nuclear Fuel” (SNFD 2017 report) at the end of 2017. This report went through international peer and domestic panel reviews, thus become an important safety assessment report at the current stage. Based on the well-developed KBS-3 disposal concepts proposed by SKB, SNFD 2017 report considers granite as the bedrock for the repository and demonstrates Taipower’s capability in developing a safe disposal program for spent nuclear fuels in Taiwan. This project aims at studying the main review phase conducted by Swedish Radiation Safety Authority (SSM) on SKB’s license application for spent nuclear fuel repository at Forsmark (SR-Site). A total of 30 review reports was published by SSM in the main review phase during 2013 to 2016. These will be grouped into 4 categories, including site characteristics, repository design, safety analysis, and radiation protection and regulations, for detailed examination. Findings from the study will be helpful in strengthening the technical reviewing capability of the Authority (FCMA). In addition to studying review reports, a few verification tasks on important safety features of the repository are included in the project. These tasks are intended to be conducted independently such that major findings from SNFD 2017 and/or international collaborated researches can be compared/verified. Thus, three technical sub-studies, namely, analysis on the spatial heterogeneity of repository bedrock and isostatic stress on canister, experimental determination on material properties of buffer/backfill material and simulations on the long-term deformation in the near-field, and requirements on the proportioning and properties of low pH cement concrete in application to 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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