Community Research and Development Information Service - CORDIS

Abstract

One of the main concerns of tritium-material interaction is the determination of tritium recycling from, tritium inventory in, and tritium permeation through, the first wall or other plasma facing components of a thermonuclear fusion reactor. Numerical codes, such as TIRP, have been developed to calculate these properties. These codes need several tritium-material interaction parameters as input data: diffusivity D, solubility K(s), heat of transport Q, surface recombination rate K(r), trap concentration c(T) and energy difference between trap and solution sites E(T). This report presents a literature study of D, K(s) and Q, an equation for the calculation of K(r) and some remarks on c(T) and E(T). In addition, a discussion of the effectiveness of permeation barriers on fusion reactor materials is included.

Additional information

Authors: REITER F, JRC Ispra (IT);FORCEY K S, JRC Ispra (IT);GERVASINI G, CNR, Istituto di Fisica del Plasma, Milano (IT)
Bibliographic Reference: Paper presented: XII National Conference on Vacuum Science and Technology, Bolzano (IT), March 23-26, 1993
Availability: Available from (1) as Paper EN 37495 ORA
Record Number: 199310719 / Last updated on: 1994-11-29
Category: PUBLICATION
Original language: en
Available languages: en