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Abstract

This paper describes the PETRA hot cell facility currently undergoing commissioning tests at the JRC-Ispra Establishment and illustrates the possibilities and objectives of experimental work that can be carried out in the field of radioactive waste management. The facility includes the typical HA-process steps of nuclear fuel reprocessing, i.e. dissolution, filtration, co-decontamination with on-line solvent regeneration) for the production of significant quantities of both medium and high level liquid and solid waste. These are to be used primarily for optimisation, certification and demonstation studies at full radioactivity levels, for the study of safety and reliability of waste confinement and disposal. The facility operates on fuel batches of 6 kg low enriched U equivalent in a sequential processing mode. The waste streams can be treated by further extraction, concentration, precipitation, denitration and vitrification either as a whole or as separate fractions.

Additional information

Authors: DWORSCHAK H, JRC ISPRA ESTAB. (IT);ENEA CASACCIA (IT);GIRARDI F, JRC ISPRA ESTAB. (IT);ENEA CASACCIA (IT);GROSSI G JRC ISPRA ESTAB. (IT), JRC ISPRA ESTAB. (IT);ENEA CASACCIA (IT);ENEA CASACCIA (IT), JRC ISPRA ESTAB. (IT);ENEA CASACCIA (IT)
Bibliographic Reference: PAPER PRESENTED: JOINT INTERNATIONAL WASTE MANAGEMENT, KYOTO (JP), OCT. 23-28, 1989 AVAILABLE FROM COMMISSION OF THE EUROPEAN COMMUNITIES, DG XIII-C-3, L-2920 LUXEMBOURG AS PAPER EN 34551 ORA
Availability: Can be ordered online
Record Number: 1989128075700 / Last updated on: 1990-11-09
Category: PUBLICATION
Available languages: en