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Abstract

Two methods to recover the tritium from the Li-17Pb-83 liquid breeder used in the breeding blanket design developed at JRC-Ispra for INTOR/NET are outlined and discussed. They are (i) direct tritium pumping from stagnant and stirred breeder, and (ii) tritium extraction from a packed or bubble column by flushing an inert gas in countercurrent to the breeder. The lack of experimental data on tritium solubility and diffusion and on other physico-chemical properties of Li-17Pb-83 do not yet enable us to choose among the two schemes. However, at present the second appears more promising.

Additional information

Authors: POLCARO A M, JRC ISPRA ESTAB. (ITALY);INSTITUTE OF APPLIED CHEMISTRY AND METALLURGY, UNIVERSITY OF CAGLIARI (ITALY);RICCI P F, JRC ISPRA ESTAB. (ITALY);INSTITUTE OF APPLIED CHEMISTRY AND METALLURGY, UNIVERSITY OF CAGLIARI (ITALY);VIOLA A JRC ISPRA ESTAB. (ITALY), JRC ISPRA ESTAB. (ITALY);INSTITUTE OF APPLIED CHEMISTRY AND METALLURGY, UNIVERSITY OF CAGLIARI (ITALY);INSTITUTE OF APPLIED CHEMISTRY AND METALLURGY, UNIVERSITY OF CAGLIARI (ITALY), JRC ISPRA ESTAB. (ITALY);INSTITUTE OF APPLIED CHEMISTRY AND METALLURGY, UNIVERSITY OF CAGLIARI (ITALY);PERINI G, JRC ISPRA ESTAB. (ITALY);INSTITUTE OF APPLIED CHEMISTRY AND METALLURGY, UNIVERSITY OF CAGLIARI (ITALY)
Bibliographic Reference: NUCLEAR ENGINEERING AND DESIGN/FUSION, VOL. 1 (1984), NO. 2, PP. 159-165
Record Number: 1989122095900 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en