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--.