Assessment of Concrete Barrier Durability for Nuclear Spent Fuel

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Project title

Code/計畫編號

NSC96-NU-7019-001

Translated Name/計畫中文名

混凝土工程障壁耐久性評估模式

Project Coordinator/計畫主持人

Chung-Chia Yang

Funding Organization/主管機關

National Science and Technology Center for Disaster Reduction

Department/Unit

Institude of Optoelectronic Sciences

Website

https://www.grb.gov.tw/search/planDetail?id=1401133

Year

2007

Start date/計畫起

01-01-2007

Expected Completion/計畫迄

31-12-2007

Bugetid/研究經費

458千元

ResearchField/研究領域

原子能工程
土木水利工程

為探討工程障壁劣化及混凝土包裝容器材料之耐久性。本計劃將採三種純水泥混凝土(約w/c=0.35, 0.45, 0.55)，且基於耐久性之考量，各水灰比中分別添加 20%飛灰、30%爐灰、40%爐石粉取代水泥用量，共9 種配比進行實驗。因核燃料混凝土包裝容器使用之混凝土材料需長期處於約95℃之溫度環境下，本計劃混凝土試體於水中養護91 天以後，分別貯存於室溫及95℃之溫度環境下，至各貯存時間(6 個月、12 個月、18 個月、24 個月、及30 個月)再進行各項實驗。將進行之實驗含加速氯離子傳輸試驗(Accelerated chloride migration test; ACMT)、鹽水浸泡試驗（Ponding test；AASHTO T259）、及健度試驗。使用氯離子擴散方程式加入溫度效應，探討工程障壁劣及混凝土包裝容器材料之耐久性，並驗證其破壞機制且以電腦模擬之。 In order to study the durability of concrete barrier and storage cask of nuclear spent fuel, the plain cement concrete and concrete containing different type of mineral admixtures (fly ash, slag, and fly ash-slag) with w/b ratios of 0.35, 0.45, and 0.55 were used. To consider the concrete durability, twenty percent, thirty percent, and forty percent of cement was replaced by fly ash, slag, and fly ash-slag, respectively, in each w/c ratio. Since the service temperature of concrete for dry storage cask of nuclear spent fuel is about 95℃, the specimens will cured in water (23 ℃) for 91 days, and then store in air and the 95℃ temperature conditions until the time of testing. After store in air and in an oven at T 凍95℃ for 6, 12, 18, 24, and 30 months, the ACMT (Accelerated chloride migration test), the ponding test (AASHTO T259), and the sound test will be used to investigate the concrete durability. The chloride migration coefficient for concrete is calculated using the constant flux from the Nernst-Planck equation in ACMT. The chloride content and penetration depth of concretes were measured after the ponding test, and the Fick』s second law of diffusion was fitted to the data from experiment to determine the diffusion coefficient. The chloride migration coefficient and the diffusion coefficient will be used to assess the influence of the T 凍95℃ effect on the durability of concrete barrier and storage cask of nuclear spent fuel.

Keyword(s)

工程障壁
混凝土包裝容器
溫度
加速氯離子傳輸試驗
混凝土耐久性表C011
Concrete barrier
Storage cask
Temperature
Accelerated chloridemigration test
Concrete durability

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Assessment of Concrete Barrier Durability for Nuclear Spent Fuel

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