Community Research and Development Information Service - CORDIS

Abstract

Detritiation studies are critical for assessing the feasibility and costs of the International Tokamak Experimental Reactor (ITER) disposal plan for tritiated waste. A flexible apparatus has been commissioned for studying the detritiation of hard waste samples, by heating, melting, or dissolving them in molten metal. It is installed in a new laboratory approved for the simultaneous handling of tritium and beryllium. RF heating means the specimen temperature is limited only by the crucible material. A filter confines beryllium contamination to the silica glass specimen tube.

There is independent control of carrier gas flow rate and pressure at any value between 1E-7 mbar and 1 bar. All tubing is warmed to allow the use of wet carrier gases, and to reduce tritium memory. No organic materials are used. A specially constructed low-memory bakable ionization chamber and all-glass bubbler-set enable sensitive measurements of the tritium outgassing with minimised memory effects. .

Additional information

Authors: EDWARDS R A H, JRC Ispra (IT);PACENTI P, JRC Ispra (IT)
Bibliographic Reference: Paper presented: Belgirate (IT), May 1995
Availability: Available from (1) as Paper EN 39066 ORA
Record Number: 199512154 / Last updated on: 1996-01-26
Category: PUBLICATION
Original language: en
Available languages: en