Plasma diagnostic requirements for Tokamak Fusion Core Experiment and International Tokamak Reactor

Conference · Wed May 01 04:00:00 EDT 1985 · Rev. Sci. Instrum.; (United States)

OSTI ID:5197039

Young, K M

The preconceptual design phase of the Tokamak Fusion Core Experiment (TFCX) and Phase IIA of the International Tokamak Reactor (INTOR) workshop have included reassessment of the plasma diagnostic requirements for the large rf heated, neutron-generating plasmas in these devices. The three principal components of the work have been (i) to reassess the present level of diagnostic capability, (ii) to identify the diagnostics required for measurement before and during the burn phases of the two devices and (iii) to define a program of research and development activities of new or upgraded diagnostics. Both devices are expected to start operation in the early 1990's; it is, therefore, necessary to set up development programs on US tokamaks to evaluate fusion product measurements, and to establish capability of reliable, radiation-hardened instruments. The adequacy of the operational information available with very limited access through the shielding and structure of the tokamaks also must be determined. This paper describes the present plans for these programs.

• Research Organization: Princeton Univ., NJ
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 5197039
• Report Number(s): CONF-840922-
• Conference Information: Journal Name: Rev. Sci. Instrum.; (United States) Journal Volume: 56:5
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700102* -- Fusion Energy-- Plasma Research-- Diagnostics
BARYONS
ELEMENTARY PARTICLES
FERMIONS
HADRONS
INTOR TOKAMAK
NEUTRONS
NUCLEAR REACTIONS
NUCLEONS
NUCLEOSYNTHESIS
PLASMA DIAGNOSTICS
RESEARCH PROGRAMS
SYNTHESIS
TFCX REACTORS
THERMONUCLEAR REACTIONS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS