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Title: Neutron dosimetry for the TFTR Lithium-Blanket-Module program

Conference ·
OSTI ID:5223413

The Tokamak Fusion Test Reactor (TFTR) Lithium Blanket Module (LBM) program is a first-of-a-kind neutronics experiment involving a prototypical fusion reactor blanket module with a distributed neutron source from the plasma of the TFTR at Princeton Plasma Physics Laboratory. The objectives of the LBM program are: (1) to test the capabilities of neutron transport codes when applied to fusion test reactor blanket conditions, and (2) to obtain tritium breeding performance data on a typical design concept of a fusion-reactor blanket. This paper addresses the issues relative to the measurement of neutron fields in the LBM, presents the results of preliminary design studies concerning neutron measurements and also presents the results of blanket mockup experiments performed at the Idaho National Engineering Laboratory (INEL).

Research Organization:
EG and G Idaho, Inc., Idaho Falls (USA); General Atomic Co., San Diego, CA (USA)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
5223413
Report Number(s):
EGG-M-13082; CONF-820406-15; ON: DE82017733
Resource Relation:
Conference: Topical meeting on fast, thermal and fusion reactor experiments, Salt Lake City, UT, USA, 12 Apr 1982; Other Information: Portions of document are illegible
Country of Publication:
United States
Language:
English