110年用過核子燃料最終處置場址及工程障壁特性之管制技術研究;Development of Control Capability on Siting and Engineered Barrier Properties for Final Disposal Facility of Spent Nuclear Fuel

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Please use this identifier to cite or link to this item: http://ir.lib.ncu.edu.tw/handle/987654321/87191

Title:	110年用過核子燃料最終處置場址及工程障壁特性之管制技術研究;Development of Control Capability on Siting and Engineered Barrier Properties for Final Disposal Facility of Spent Nuclear Fuel
Authors:	張瑞宏;楊樹榮;黃偉慶
Contributors:	國立中央大學土木工程學系
Keywords:	用過核子燃料最終處置;處置設施場址特性導則;工程障壁特性;Geological Disposal for Spent Nuclear Fuel;Site Characterization of Disposal Facility;Functions of Engineered Barrier
Date:	2021-12-21
Issue Date:	2021-12-23 11:29:20 (UTC+8)
Publisher:	行政院原子能委員會
Abstract:	我國用過核子燃料最終處置計畫於107年邁入第二階段之「候選場址評選與核定」，同時，行政院國家永續發展委員會108年提出「台灣永續發展目標」，亦將推動「高放射性廢棄物最終處置設施」法制作業，列為具體目標之一，可見高放廢棄物最終處置課題受到各方所矚目。110年度高放最終處置的審查、驗證及管制等工作發展，將參酌核能先進國家相關法規、導則、安全要求或最終處置設施安全分析報告之審查案例，掌握安全評估關鍵要項，以持續推動我國高放最終處置設施安全分析報告導則之研擬工作，期能完備我國高放最終處置相關法規。　　本年度計畫擬針對用過核子燃料最終處置設施安全分析報告之場址特性與設施運轉內容需求，研析國際核能組織發布之高放射性廢棄物最終處置有關安全規範或導則，以及主要核能國家對於高放地質處置設施場址特性與設施運轉之相關要求與關鍵技術要項、高放地質處置安全分析報告審查案例等，研提我國用過核子燃料最終處置設施安全分析報告導則之場址特性與設施運轉專章，同時提出對於未來國內階段性安全報告審查要項之建議。此外，針對用過核子燃料最終處置場工程障壁安全評估所需的重要技術，進行實驗分析與數值模擬成果之平行驗證，包括處置罐承載分析與國際合作工程障壁研究計畫平行驗證、緩衝材料之沖蝕機制與流失量評估研析以及實驗技術建立等工作，研究成果將有助於工程障壁特性及安全功能的掌握，配合處置場址與設施運轉之審查重點，將足以提升國內高放最終處置相關管制技術與審查能力。 ;In Taiwan, the geological disposal program for spent nuclear fuel has moved to the second phase, started in 2018, of identifying potential areas for a repository site. Also, the government of Taiwan has placed “the promotion of legalization process for final disposal facility for high-level radioactive wastes” as one of the core goals in the “Taiwan Sustainable Development Goals” declared in 2019. Thus, the development of the specific guide for the safety analysis report of the geological disposal facility becomes essential. This year, the task will incorporate consultation of the guide/requirements brought up by international organizations and review of key issues encountered by various countries on their safety analysis report for geological disposal program. This will benefit the forthcoming review of the safety assessment reports to be submitted and the control of the final disposal program administered by Taipower. This study will assimilate the safety guides set up by international organizations for geological disposal facility of high-level radioactive wastes and requirements on siting characterization and facility operation for geological disposal facility employed by various countries. Based careful examination of the information, a draft on the siting characteristics and facility operation for the safety analysis report for geological disposal facility will be devised, along with suggestions on relevant major technical review issues. 　　In addition, a couple of verification tasks on important safety features of the engineered barriers are included in the study. These tasks are intended to be conducted independently such that major findings from Taipower’s safety assessment reports and/or international collaborated researches can be compared and/or verified. As a result, 2 technical sub-studies, namely, verifications on the loading analyses of canister performed by Taipower and other countries, and experimental study on the erosion mechanism of buffer and estimation of total erosion in a deposition hole, are included in this study.
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:	[Department of Civil Engineering] Research Project

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