Published 2003 | Version v1
Miscellaneous

Retention of Cs-137 on concrete samples

  • 1. Institute for Nuclear Research, PO Box 78, 1 Campului Street, 0300 Pitesti, Jud. Arges (Romania)

Description

The near-field disposal facility will be designed to provide effective containment for the radionuclides in the waste repository. Its design is based on a concept of multi-barrier containment, both physical (by steel and concrete packaging) and chemical containment. It is based on development of a uniform, beneficial aqueous condition and due both to the provision of a high sorption capacity across the repository cell and to geological isolation. The goal of this paper is to evaluate by means of DUST-MS computer code the chemical containment process (sorption capacity of backfill, distribution coefficient) of one potential contaminant which can be released from radioactive wastes conditioned form disposed in this repository, because of the dissolution/leaching processes. (authors)

Availability note (English)

Available from author(s) or Romanian Nuclear Energy Association, AREN, Str. Atomistilor 111, PO Box 53, RO-76900 Bucharest - Magurele (RO) or University Politehnica of Bucharest, Splaiul Independentei 313, Sector 6, RO-77206 Bucharest (RO)
Part of:
Programme of the International Symposium on Nuclear Energy SIEN 2003, Nuclear Power - A New Challenge

Additional details

Publishing Information

Publisher
Romanian Nuclear Energy Association, AREN
Imprint Place
Bucharest (Romania)
Imprint Title
Programme of the International Symposium on Nuclear Energy SIEN 2003, Nuclear Power - A New Challenge
Imprint Pagination
606 p.
Journal Page Range
p. 553-557

Conference

Title
SIEN 2003, International Symposium on Nuclear Energy, Nuclear Power - A New Challenge
Dates
22-25 Oct 2003
Place
Bucuresti (Romania)

Optional Information

Notes
6 refs., 3 figs., 3 tabs.