Published 1988 | Version v1
Report Open

Lithium test module on ITER: engineering design of the tritium recovery system

Description

The design presented is an overview of the tritium recovery system for a lithium module on an ITER type reactor. The design of a tritium recovery system for larger blanket units, sectors, etc. could use the information developed in this report. A goal of this design was to ensure that a reliable, integrated performance of the tritium recovery system could be demonstrated. An equally important goal was to measure and account for the tritium in the liquid lithium blanket module and its recovery system in order to validate the operation of the blanket module

Availability note (English)

Available from NTIS, PC A03/MF A01; 1 as DE88011967.

Files

19097229.pdf

Files (205.3 kB)

Name Size Download all
md5:9809f3cb3d659d2ae854149a2bdda6f6
205.3 kB Preview Download

Additional details

Publishing Information

Imprint Pagination
13 p.
Report number
CONF-880505--28

Conference

Title
3. topical meeting on tritium technology in fission, fusion and isotopic applications.
Dates
1-6 May 1988.
Place
Toronto (Canada).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19097229
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
SPECIFICATIONS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TRITIUM RECOVERY
Descriptors DEC
CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES

Optional Information

Notes
Portions are illegible in microfiche products.