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Monte Carlo hodoscope calculations. [LMFBR Safety Test Facility neutron-gamma hodoscope performance studies] [electronic resource].

Published
Los Alamos, N.M. : Los Alamos Scientific Laboratory, 1977.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 3 : digital, PDF file
Additional Creators
Los Alamos Scientific Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
A Monte Carlo calculational program is under way to determine the effectiveness of a neutron-gamma hodoscope as an instrument for viewing fuel motion and density changes in a central test region of the Safety Test Facility during a simulated fast reactor excursion. The hodoscope is a 5 cm. wide stainless steel plate inserted radially through the nickel reflector to the inner boundary of the reactor core. A 1-cm. diameter hole extends through the hodoscope, exposing the fuel test region at the center of the reactor. The information required from the calculations is the relative magnitude of the fast neutron and gamma flux at a detector situated outside the reactor along the axis of the slit (or hole) in the hodoscope.
Report Numbers
E 1.99:la-ur-76-1887
E 1.99: conf-770401-1
conf-770401-1
la-ur-76-1887
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
01/01/1977.
"la-ur-76-1887"
" conf-770401-1"
5. international conference on reactor shielding, Knoxville, TN, USA, 18 Apr 1977.
Soran, P.D.; Cashwell, E.D.; Everett, C.J.; Macdonald, J.L., Schrandt, R.
Funding Information
W-7405-ENG-36
View MARC record | catkey: 14675240