低放射性廢棄物處置設施工程障壁由混凝土所組成，不同於一般混凝土結構用途，其服務年限需長達數百年之久。考量未來國內最終處置場之場址可能位於濱海區域，混凝土容器長期處於此環境下，對混凝土所造成之劣化與耐久性的影響顯著。
　　本研究延續先前研究團隊製作用於低放射性廢棄物處置容器用混凝土桶身及填充材料之配比HIC-C與配比HIC-M及配比C與配比M進行單一方向氯離子入侵濃度試驗，以表面氯離子濃度及擴散係數隨時間長期發展趨勢，進行配比之服務年限推估，且利用信賴區間概念與亂數模擬方法，推估盛裝容器混凝土在服務年限內發生腐蝕破壞的風險。
為提升低放射性廢棄物處置盛裝容器用混凝土之品質，延續先前研究團隊所採用80℃(三天及四天)及本研究新增90℃(兩天及三天)之熱養護方法製作試體，進行抗壓強度、孔隙率、乾縮、壓力下水貫入深度、氮氣吸附及電阻率試驗，並將結果與23℃常溫養護試體加以比較，藉由統計方法針對不同養護方式之主要實驗結果進行單因子變異數分析，整合試驗結果顯示，高溫養治兩種混凝土配比之各項性質顯著優於常溫養治混凝土，且高溫養治試體中，以80℃養護四天為較佳養護方式。
　　利用非破壞且快速量測混凝土表面電阻方式，針對可能具有瑕疵之混凝土試體進行電阻量測，將試驗結果藉由統計分析，結果顯示使用非破壞性表面電阻檢測作為容器混凝土不同階段驗收檢驗方法應具可行性。

　　The concrete used for making containers for low-level radioactive wastes is different from typical structural concrete that it is subjected to a prolonged service period.
　　This study extends the investigations on the mixes of HIC-C, HIC-M and mixes C and M used for highly integrated containers (HIC) by continuing measurements on the surface chloride ion concentration and diffusion coefficient of these mixes, such that the long-term behavior of chloride ingress into the mixes is carefully evaluated.
　　In order to improve the performance of the concrete mixes, specimens were thermally cured at 80℃ and 90℃ for 2 to 4 days and then tested for compressive strength, porosity, drying shrinkage, water penetration depth, gas adsorption and electrical resistivity. And the results were compared with the 23℃ normal temperature cured test specimens. Based on statistical analysis results, the concrete mixes cured at high temperature are found to show improved quality than those cured at normal temperature. with the 4-day curing at 80℃ having the most improvement.
　　Using the non-destructive and rapid measurements on concrete surface resistance, it was able to differentiate concrete specimens with crack and/or damage. Statistical analysis results indicate that surface resistance can be used as a means of acceptance measurement for concrete containers.

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