Community Research and Development Information Service - CORDIS

Abstract

This report describes studies carried out on five batches of hulls resulting from the reprocessing of fuel from the Prototype Fast Reactor at Dounreay. Direct immobilization in cement and decontamination have been examined as possible routes for treating the hulls, and as a background the activities on them have been characterized. Concerning decontamination a number of low temperature chemical techniques have been used to remove actinides and fission products from the hulls: nitric acid at reflux temperature, nitric acid with ceric ions added, alkaline permanganate solution, and oxalic acid with hydrogen peroxide corrosion inhibitor. The preferred route is that involving nitric acid alone, because it might be possible to recycle the decontamination liquor to the reprocessing plant, routing the fission products and several of the actinides to the high level waste, while recovering the plutonium. For immobilization 10 mm sections of hulls have been immobilized in two mixtures of Portland cement with sand or blast furnace slag. The activities released on leach testing these blocks have been compared with those from leaching bare hulls. In all, the preliminary studies suggested that cement was a satisfactory matrix for immobilizing hulls and that the BFS/OPC was the better formulation.

Additional information

Authors: BIDDLE P, AERE HARWELL, OXON (UK);BROWN P E, AERE HARWELL, OXON (UK);REES J H AERE HARWELL, OXON (UK), AERE HARWELL, OXON (UK)
Bibliographic Reference: EUR 10516 EN (1986) MF, 89 P., BFR 150, BLOW-UP COPY BFR 450, EUROFFICE, LUXEMBOURG, POB 1003
Availability: Can be ordered online
Record Number: 1989124137200 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en