Published 1977 | Version v1
Report Restricted

Design approaches for enhancing the engineering feasibility of tokamak power reactors

Creators

Description

The design approach developed in the ORNL Fusion Power Demonstration Study is reviewed. The design concepts having greatest impact on reactor feasibility by the application of current or near term technology are described briefly. These are: blanket structural material, blanket coolant, power conversion system, and pulsed electrical system. Concepts relative to the approach taken to simplify the overall reactor design are listed

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
4 p.
Report number
CONF-771109--80

Conference

Title
ANS winter meeting.
Dates
27 Nov - 2 Dec 1977.
Place
San Francisco, CA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
9381081
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BREEDING BLANKETS; COOLANTS; EFFICIENCY; SPECIFICATIONS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES
Descriptors DEC
CLOSED PLASMA DEVICES; REACTOR COMPONENTS; THERMONUCLEAR DEVICES