Source-to-incident-flux relation in a tokamak blanket module [electronic resource].

Published:: Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1981.
Physical Description:: Pages: 4 : digital, PDF file
Additional Creators:: United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

The next-generation tokamak experiments, including the Tokamak Fusion Test Reactor (TFTR), will utilize small blanket modules to measure performance parameters such as tritium breeding profiles, power deposition profiles, and neutron flux profiles. Specifically, a neutron calorimeter (simply a neutron moderating blanket module) which allows one to infer the incident 14 MeV flux based on measured temperature profiles has been proposed for TFTR. The problem addressed here is how to relate this total scalar flux to the fusion neutron source; this relation is necessary since the calorimeter is proposed as a total fusion energy monitor. The methods and assumptions presented here will be valid for the TFTR Lithium Breeding Module (LBM), as well as other modules on larger tokamak reactors.

Report Numbers:

E 1.99:conf-810606-82
conf-810606-82

Subject(s):

Plasma Physics And Fusion Technology

Other Subject(s):

Note:

Published through SciTech Connect.
01/01/1981.
"conf-810606-82"
"DE81026524"
American Nuclear Society's annual meeting, Miami Beach, FL, USA, 7 Jun 1981.
Imel, G.R.
EG and G Idaho, Inc., Idaho Falls (USA)

Funding Information:

AC07-76ID01570

View MARC record | catkey: 14754078