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Title: Control of tritium permeation through fusion reactor strucural materials

Conference ·
OSTI ID:6425978

The intention of this paper is to provide a brief synopsis of the status of understanding and technology pertaining to the dissolution and permeation of tritium in fusion reactor materials. The following sections of this paper attempt to develop a simple perspective for understanding the consequences of these phenomena and the nature of the technical methodology being contemplated to control their impact on fusion reactor operation. Considered in order are: (1) the occurrence of tritium in the fusion fuel cycle, (2) a set of tentative criteria to guide the analysis of tritium containment and control strategies, (3) the basic mechanisms by which tritium may be released from a fusion plant, and (4) the methods currently under development to control the permeation-related release mechanisms. To provide background and support for these considerations, existing solubility and permeation data for the hydrogen isotopes are compared and correlated under conditions to be expected in fusion reactor systems.

Research Organization:
Argonne National Lab., IL (USA)
DOE Contract Number:
W-31-109-ENG-38
OSTI ID:
6425978
Report Number(s):
CONF-781109-12; TRN: 79-007518
Resource Relation:
Conference: Environmental control symposium, Washington, DC, USA, 28 Nov 1978
Country of Publication:
United States
Language:
English