A STUDY ON ALKALI AGGREGATE REACTION IN NUCLEAR POWER RELATING FACILITIES

原子力施設におけるアルカリ骨材反応の一考察

An application of advanced knowledge on alkali aggregate silica reaction(ASR)for new construction and ageing management of nuclear-power-relating-facilities is discussed. At first, the concept of ASR expansion in nuclear-power-relating-facilities is proposed. Then, the characteristics and limit of various expansion tests are compared and critically discussed. Moreover, considering the quantification of long term ASR expansion, suitable condition of concrete prism test(CPT)enabling the quantitative estimation is introduced. In CPT, the expansion is accelerated by alkali boosting and higher temperature and alkali-wrapping is a promising method avoiding alkali leaching and keeping stable moisture supply. In this study, the expansion behaviors of CPT are described by three parameters, i.e. ultimate expansion, expanding speed, time to start expansion, and the dependencies on alkali amount and temperature are estimated. Then, expansion behavior estimation is become possible to estimate in any alkali amounts and environmental temperature.原子力施設の新設と高経年化対策に最新のアルカリ骨材反応(ASR)の知見を適用することを議論する。まず、原子力施設でのASR膨張の考え方を提案する。そのうえで、各種の膨張試験の特徴と限界を比較・議論する。さらに、長期間にわたるASR膨張の定量化を念頭に、これが可能となるコンクリートプリズム試験(CPT)の最適な条件を提示する。CPTはアルカリ量と温度で膨張促進するが、アルカリ溶液で湿らせた紙で巻くことで、アルカリ溶脱と水分供給を制御できる。CPTの膨張挙動を終局膨張量、膨張速度、膨張開始時間の三つのパラメータで記載し、各々のアルカリ量・温度依存性を求めることで、任意のアルカリ量と温度環境での膨張を予測する手法を提案する。

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  • English
  • Japanese

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  • Accession Number: 01563207
  • Record Type: Publication
  • Source Agency: Japan Science and Technology Agency (JST)
  • Files: TRIS, JSTAGE
  • Created Date: Apr 23 2015 10:58AM