Documents in the NTIS Technical Reports collection are the results of federally funded research. They are directly submitted to or collected by NTIS from Federal agencies for permanent accessibility to industry, academia and the public.  Before purchasing from NTIS, you may want to check for free access from (1) the issuing organization's website; (2) the U.S. Government Printing Office's Federal Digital System website; (3) the federal government Internet portal; or (4) a web search conducted using a commercial search engine such as
Accession Number DE2013-1081824
Title Physics and Engineering Assessments of Spherical Torus Component Test Facility.
Publication Date 2013
Media Count 8p
Personal Author C. Kessel C. A. Neumeyer D. J. Strickler P. Rutherford P. J. Fogarty Y. K. M. Peng
Abstract Successful development of practical fusion energy will require research and development that combine fundamental and applied science. Component Test Facilities (CTF) based on ST, aimed at advancing the required fusion engineering science and encouraged by recent scientific progress, will necessarily entail similarly combined efforts. A recent USDOE Office of Science plan identified a CTF that would be created following the International Thermonuclear Experimental Reactor (ITER) construction to address this goal. Data from CTF will determine how full steady state fusion conditions affects plasma chamber materials and components, and limits their operating life. This will in turn establish the engineering science knowledge base needed to support a decision to build a demonstration power plant (DEMO) to produce net electrical output. The plan of this paper is as follows: the CTF fusion engineering science mission and required conditions are summarized in Section 2. The engineering design features to achieve these with an ST CTF is presented in Section 3. The most recent results from ST research, as a basis for the present CTF concept, are summarized in Section 4. The fusion plasma and engineering science landscape of the compact ST CTF, calculated using a new ST systems code, will be presented in Section 5. The CTF scientific database needs are identified in Section 6 in reference to the latest progress in ST research. The requirements in fusion engineering science for the baseline CTF operation and control, including the single-turn normal conducting TF coil center leg, will also be covered in Section 6. The paper closes with a conclusion in Section 7 of the key results of the study, and a discussion of the scientific and engineering implications of CTF.
Keywords Design
Plasma confinement
Research and development
Test facilities
Thermonuclear reactors
Tokamak devices

Source Agency Technical Information Center Oak Ridge Tennessee
NTIS Subject Category 77A - Thermonuclear Fusion Devices
46G - Plasma Physics
Corporate Author Oak Ridge National Lab., TN.
Document Type Technical report
Title Note N/A
NTIS Issue Number 1323
Contract Number DE-AC05-00OR22725

Science and Technology Highlights

See a sampling of the latest scientific, technical and engineering information from NTIS in the NTIS Technical Reports Newsletter

Acrobat Reader Mobile    Acrobat Reader