Published 1989 | Version v1
Book

Repository source term for vitrified high level waste

  • 1. Harwell Lab., Didcot, Oxon OX11 ORA (UK)

Description

The authors describe the concentrations in aqueous solutions of Tc, Np, Pu and Am measured, using doped glasses, in the presence of various possible components of a future repository for vitrified high-level waste. The experiments were carried out under the reducing conditions anticipated in a repository. One possible repository design would incorporate a 20cm thick iron overpack round the glass cylinders and a backfill of Ordinary Portland Cement (OPC) and Pulverised Fuel Ash (PFA)

Additional details

Publishing Information

Publisher
Materials Research Society.
Imprint Place
Pittsburgh, PA (USA)
ISBN
0-931837-97-9
Imprint Title
Scientific basis for nuclear waste management XII
Imprint Pagination
1001 p.
Series
Materials Research Society symposium proceedings. Volume 127.
Journal Page Range
p. 137-144.

Conference

Title
12. international symposium on the scientific basis for nuclear waste management.
Dates
10-13 Oct 1988.
Place
Berlin (Germany, F.R.).

Optional Information

Secondary number(s)
CONF-881066--.