Concrete Design for Sealing a Nuclear Waste Repository

International Concrete Abstracts Portal

The International Concrete Abstracts Portal is an ACI led collaboration with leading technical organizations from within the international concrete industry and offers the most comprehensive collection of published concrete abstracts.

  


Title: Concrete Design for Sealing a Nuclear Waste Repository

Author(s): Robert D. Allen and Harold L. Benny

Publication: Concrete International

Volume: 9

Issue: 8

Appears on pages(s): 53-58

Keywords: basalt; bentonite; bulkheads; concretes; grouting; sealing; portland cements; radioactive wastes; silica; structural design; Design

DOI:

Date: 8/1/1987

Abstract:
A candidate site for radioactive waste isolation in basalt rock also calls for use of concrete or grout. Portland cement, basalt aggregate, and finely divided reactive silica are the most likely constituents of concrete for bulkhead design.




  

Edit Module Settings to define Page Content Reviewer