hrcak mascot   Srce   HID

Review article

CHARACTERIZATION OF BENTONITE FOR ENGINEERED BARRIER SYSTEMS IN RADIOACTIVE WASTE DISPOSAL SITES

Dubravko Domitrović
Helena Vučenović
Biljana Kovačević Zelić

Fulltext: croatian, pdf (3 MB) pages 19-27 downloads: 769* cite
APA 6th Edition
Domitrović, D., Vučenović, H. & Kovačević Zelić, B. (2012). ISPITIVANJE SVOJSTAVA BENTONITA KAO INŽENJERSKE BARIJERE U ODLAGALIŠTIMA RADIOAKTIVNOG OTPADA. Rudarsko-geološko-naftni zbornik, 24 (1), 19-27. Retrieved from https://hrcak.srce.hr/107797
MLA 8th Edition
Domitrović, Dubravko, et al. "ISPITIVANJE SVOJSTAVA BENTONITA KAO INŽENJERSKE BARIJERE U ODLAGALIŠTIMA RADIOAKTIVNOG OTPADA." Rudarsko-geološko-naftni zbornik, vol. 24, no. 1, 2012, pp. 19-27. https://hrcak.srce.hr/107797. Accessed 20 Oct. 2019.
Chicago 17th Edition
Domitrović, Dubravko, Helena Vučenović and Biljana Kovačević Zelić. "ISPITIVANJE SVOJSTAVA BENTONITA KAO INŽENJERSKE BARIJERE U ODLAGALIŠTIMA RADIOAKTIVNOG OTPADA." Rudarsko-geološko-naftni zbornik 24, no. 1 (2012): 19-27. https://hrcak.srce.hr/107797
Harvard
Domitrović, D., Vučenović, H., and Kovačević Zelić, B. (2012). 'ISPITIVANJE SVOJSTAVA BENTONITA KAO INŽENJERSKE BARIJERE U ODLAGALIŠTIMA RADIOAKTIVNOG OTPADA', Rudarsko-geološko-naftni zbornik, 24(1), pp. 19-27. Available at: https://hrcak.srce.hr/107797 (Accessed 20 October 2019)
Vancouver
Domitrović D, Vučenović H, Kovačević Zelić B. ISPITIVANJE SVOJSTAVA BENTONITA KAO INŽENJERSKE BARIJERE U ODLAGALIŠTIMA RADIOAKTIVNOG OTPADA. Rudarsko-geološko-naftni zbornik [Internet]. 2012 [cited 2019 October 20];24(1):19-27. Available from: https://hrcak.srce.hr/107797
IEEE
D. Domitrović, H. Vučenović and B. Kovačević Zelić, "ISPITIVANJE SVOJSTAVA BENTONITA KAO INŽENJERSKE BARIJERE U ODLAGALIŠTIMA RADIOAKTIVNOG OTPADA", Rudarsko-geološko-naftni zbornik, vol.24, no. 1, pp. 19-27, 2012. [Online]. Available: https://hrcak.srce.hr/107797. [Accessed: 20 October 2019]

Abstracts
Engineered barrier systems are used in radioactive waste disposal sites in order to provide better protection of humans and the environment from the potential hazards associated with the radioactive waste disposal. The engineered barrier systems usually contain cement or clay (bentonite) because of their isolation properties and long term performance. Quality control tests of clays are the same for all engineering barrier systems. Differences may arise in the required criteria to be met due for different application. Prescribed clay properties depend also on the type of host rocks. This article presents radioactive waste management based on best international practice. Standard quality control procedures for bentonite used as a sealing barrier in radioactive waste disposal sites are described as some personal experiences and results of the index tests (free swelling index, water adsorption capacity, plasticity limits) and hydraulic permeability of bentonite.

Keywords
bentonite; quality control; radioactive waste disposal sites

Hrčak ID: 107797

URI
https://hrcak.srce.hr/107797

[croatian]

Visits: 1.032 *