Design of tritium breeding experiments for the tokamak fusion test reactor [electronic resource].
- Published
- Princeton, N.J. : Princeton University, 1981.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 9 : digital, PDF file
- Additional Creators
- Princeton University and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Among intense fusion-neutron generators of the 1980's, the unique features of the TFTR are a geometrically extended D-T fusion-neutron source and a neutron spectrum, including backscattered neutrons, characteristic of a practical toroidal fusion reactor. It is planned to install a tritium-breeding module on the TFTR in order to take advantage of this opportunity to obtain reactor-relevant integral neutronics data and breeding rate profiles. These data will be combined with the measured neutron source parameters and the spatially dependent fusion-neutron fluence for comparison with the predictions of neutronics design codes. The results of this program will help determine the blanket coverage factors needed to achieve tritium self-sufficiency in future toroidal reactors. A preliminary conceptual design of a TFTR blanket module has been completed, utilizing lithium oxide as the tritium breeding material.
- Report Numbers
- E 1.99:pppl-1749
E 1.99: conf-800427-21
conf-800427-21
pppl-1749 - Subject(s)
- Other Subject(s)
- Breeding
- Tritium
- Tftr Reactors
- Breeding Ratio
- Fuel Cycle
- Neutron Sources
- Neutron Transport
- Beta Decay Radioisotopes
- Beta-Minus Decay Radioisotopes
- Conversion Ratio
- Hydrogen Isotopes
- Isotopes
- Light Nuclei
- Neutral-Particle Transport
- Nuclear Fuel Conversion
- Nuclei
- Odd-Even Nuclei
- Particle Sources
- Radiation Sources
- Radiation Transport
- Radioisotopes
- Thermonuclear Reactors
- Tokamak Type Reactors
- Years Living Radioisotopes
- Note
- Published through SciTech Connect.
01/01/1981.
"pppl-1749"
" conf-800427-21"
Tritium technology in fission, fusion, and isotopic applications, Dayton, OH, USA, 29 Apr 1980.
Jassby, D.L.; Caldwell, C.S.; Pettus, W.G.; Schmotzer, J.K.; Lewis, R.H.; Thornton, T.A.; Welfare, F.G.; Womack, R.E. - Funding Information
- AM02-76CH03023
View MARC record | catkey: 14755951