Published 1987 | Version v1
Book

Laboratory scale modelling of the Finnish reactor waste disposal systems

  • 1. Technical Research Centre of Finland, Otakaari 3 A, SF-02150 Espoo

Description

The aim of the work is to model experimentally the inner constructions of two reactor waste repositories. The modelling of the multibarrier systems was started on a laboratory scale using the same principal materials as in the Finnish reactor waste disposal concepts. Migration of cesium, cobalt and strontium was studied in various combinations of the following materials: bituminized resin, cemented resin, concrete, crushed rock and water. Sample preparation is described and activity profiles of some samples are demonstrated in the paper. The maximum sample age was 224 d. Distinct diffusion was observed with strontium in crushed tonalite and rapakivigranite, and with cesium in crushed rapakivigranite and in concrete. Cobalt showed no mobility

Additional details

Publishing Information

Publisher
University of Arizona Nuclear Engineering Dept.
Imprint Place
Tucson, AZ (USA)
Imprint Title
Waste management '87: Waste isolation in the US, technical programs, and public education
Journal Page Range
p. 512-520.

Conference

Title
Waste management '87.
Dates
1-5 Mar 1987.
Place
Tucson, AZ (USA).