Journals / Teknik Dergi / 2016 / Cilt: 27 - Sayı: 3

Geotechnical Assessment of Compacted Sand Bentonite Mixtures to be Utilized in Underground Nuclear Waste Repositories and Barrier Design

Yeraltı Nükleer Atık Haznelerinde Kullanılabilecek Sıkıştırılmış Kum Bentonit Karışımlarının Geoteknik Değerlendirmesi ve Bariyer Tasarımı

Pages
7477–7496
Publication Date
2016-07-01
DOI
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AI Summary & Key Takeaways

AI Insight
⚡ TL;DR(Too Long; Didn't Read)

Sand bentonite barrier design was performed for the optimum seal selected as a function of the axial stress applied to the barrier and barrier length-to-radius ratio (L/a).

📌 3 Key Takeaways

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Objective & Hypothesis:This study assesses the mechanical and hydrological performance of compacted sand bentonite mixtures to be utilized in sealing underground nuclear waste repositories.
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Key Findings & Data:In order to assess the performance of this material and to obtain an optimum sand bentonite mixture, a variety of laboratory tests, namely, compaction, falling head permeability, swelling, unconfined compression and shear strength tests were performed on sand bentonite mixtures possessing bentonite contents ranging from 5% to 15%.
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Conclusion & Impact:Sand bentonite barrier design was performed for the optimum seal selected as a function of the axial stress applied to the barrier and barrier length-to-radius ratio (L/a).
🔬Design:Research Article
📍Scope:Comprehensive Sample
⚙️Variables:Kum bentonit karışımı · nükleer atık depolaması · bariyer tasarımı

Abstract

This study assesses the mechanical and hydrological performance of compacted sand bentonite mixtures to be utilized in sealing underground nuclear waste repositories. In order to assess the performance of this material and to obtain an optimum sand bentonite mixture, a variety of laboratory tests, namely, compaction, falling head permeability, swelling, unconfined compression and shear strength tests were performed on sand bentonite mixtures possessing bentonite contents ranging from 5% to 15%. Sand bentonite barrier design was performed for the optimum seal selected as a function of the axial stress applied to the barrier and barrier length-to-radius ratio (L/a).

Özet

Bu çalışmada, yeraltı nükleer atık depolama haznelerinin sızdırmazlığının sağlanması için geoteknik ve hidrolojik açıdan sıkıştırılmış kum bentonit izolasyon malzemesi tasarlanması amaçlanmaktadır. Optimum karışım miktarını belirlemek için %5 ile %15 oranları aralığında bentonit içeren kum bentonit karışımları üzerinde kompaksiyon, düşen seviyeli hidrolik iletkenlik, şişme basıncı, serbest basınç ve basit kesme deneyleri yapılmıştır. Seçilen optimum kum bentonit bariyer karışımının tasarımı, bariyere uygulanan düşey gerilmenin ve bariyer yükseklik-yarıçap oranının (L/a) fonksiyonu olarak yapılmıştır.

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Cite This Article

AKGÜN, H., ADA, M., KOÇKAR, M. K. (2016). Geotechnical Assessment of Compacted Sand Bentonite Mixtures to be Utilized in Underground Nuclear Waste Repositories and Barrier Design. Teknik Dergi, Cilt: 27 - Sayı: 3, 7477–7496. https://ajindex.com/articles/51313

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References (8)

  1. TEÜD Şti., Türkiye’nin Elektrik Üretimi ve Dağıtımı, Türkiye Elektrik Üretim ve Dağıtım Şirketi, Ankara, 1999. IAEA (International Atomic Energy Agency), “Sealing of Underground Repositories for Radioactive Wastes”, Editörler: Gray, M., Gera, F., Wiley, J.R., Dlouhy, Z., Squires, D., International Atomic Energy Agency, Vienna, Unipub, Lanham, MD, Tech Reps Series No. 319, 1990. IAEA (International Atomic Energy Agency), “Hydrogeological Investigation of Sites for the Geological Disposal of Radioactive Waste”, Technical Reports Series No. 391, International Atomic Energy Agency, Vienna, 1999. IAEA (International Atomic Energy Agency), “The Use of Scientific and Technical Results from Underground Research Laboratory Investigations for the Geological Disposal of Radioactive Waste”, IAEA-TECDOC-1243, International Atomic Energy Agency, Vienna, 2001. IAEA (International Atomic Energy Agency), “Scientific and Technical Basis for the Geological Disposal of Radioactive Wastes”, Technical Reports Series No. 4I3, International Atomic Energy Agency, Vienna, 2003.10. OECD (Organisation for Economic Co-operation and Development), “Geological Disposal of Nuclear Waste in Perspective”, OECD, Nuclear Energy Agency (NEA), Paris, 2000. CTECH, “Conceptual Design for a Deep Geologic Repository for Used Nuclear Fuel”, CTECH Report 1106/MD18085/REP/01, 2002. SKB (Swedish Nuclear Fuel and Waste Management Co.), “Long-term Safety for KBS-3 Repositories at Forsmark and Laxemar - A First Evaluation”, Technical Report TR-06-09,
  2. SKB, Stockholm, 2006. ANDRA (French National Radioactive Waste Management Agency), “The Deep Geological Concept as Developed by ANDRA,”. ANDRA, www.andra.fr, 4 p, 2011.
  3. Pusch, R. ve Bergström A, “Highly Compacted Bentonite for Borehole and Shaft Plugging”, Proceedings of the Workshop on Borehole and Shaft Plugging, Columbus, OH, May 7–9, Organization for Economic Co-operation and Development, Paris, 161–168, 1980.
  4. Meyer, D. ve Howard, J.J., “Evaluation of Clays and Clay Minerals for Application to Repository Sealing”, ONWI-486, Office of Nuclear Waste Isolation, Battelle Memorial Institute, OH, 1983.
  5. Pusch, R., “Waste Disposal in Rock”, Developments in Geotechnical Engineering 76, Elsevier, Amsterdam, 490 s. 1994.
  6. Akgün, H., “Shear Strength of Cement-grout Borehole Plug”, In Situ, 24: 107-137, 2000.
  7. Akgün, H. ve Daemen, J.J.K., “Performance Assessment of Cement Grout Borehole Plugs in Basalt”, Engineering Geology, 37: 137-148, 1994.
  8. Akgün, H. ve Daemen, J.J.K