Published 1981 | Version v1
Journal article

Sensitivity study code for tokamak devices

  • 1. Mitsubishi At Power Ind Inc, Saitama, Jpn

Description

A FORTRAN code has been developed to conduct sensitivity study for Tokamak devices on physics and engineering parameters. This code is applicable to various kinds of tokamak systems from experimental devices to reactors. The code calculates configuration parameters, weights of components, required power supply capacity and some technological requirements as a function of main plasma parameters and machine parameters. The present version of this code had been successfully applied to parametric studies for INTOR, SPTR (Swimming Pool Tokamak Reactor) and other devices, and will be further improved

Additional details

Publishing Information

Journal Title
Proc. Symp. Eng. Probl. Fusion Res.
Journal Issue
p. 1880-1883
Series
Proc. Symp. Eng. Probl. Fusion Res.
ISSN
0145-5958

Conference

Title
9. symposium on engineering problems of fusion research.
Dates
26 - 29 Oct 1981.
Place
Chicago, IL (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14766080
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; SENSITIVITY ANALYSIS; SUPPORTS; TOKAMAK DEVICES
Descriptors DEC
CLOSED PLASMA DEVICES; MECHANICAL STRUCTURES; THERMONUCLEAR DEVICES

Optional Information

Secondary number(s)
CONF-811040--.