Second generation Research Reactor Fuel Container (RRFC-II) [electronic resource].

Published:: Washington, D.C. : United States. Dept. of Energy, 2001.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: 9 pages : digital, PDF file
Additional Creators:: Los Alamos National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

The second generation Research Reactor Fuel Counter (RRFC-II) has been developed to measure the remaining ²³⁵U content in foreign spent Material Test Reactor (MTR)-type fuel being returned to the Westinghouse Savannah River Site (WSRS) for interim storage and subsequent disposal. The fuel to be measured started as fresh fuel nominally with 93% enriched Uraniuin alloyed with A1 clad in Al. The fuel was irradiated to levels of up to 65% burnup. The RRFC-II, which will be located in the L-Basin spent fuel pool, is intended to assay the ²³⁵U content using a combination of passive neutron coincidence counting, active neutron coincidence counting, and active-multiplicity analysis. Measurements will be done underwater, eliminating the need for costly and hazardous handling operations of spent fuel out of water. The underwater portion of the RRFC-II consists of a watertight stainless steel housing containing neutron and gamma detectors and a scanning active neutron source. The portion of the system that resides above water consists of data-processing electronics; electromechanical drive electronics; a computer to control the operation of the counter, to collect, and to analyze data; and a touch screen interface located at the equipment rack. The RRFC-II is an improved version of the Los Alamos-designed RRFC already installed in the SRS Receipts Basin for Offsite Fuel. The RRFC-II has been fabricated and is scheduled for installation in late FY 2001 pending acceptance testing by Savannah River Site personnel.

Report Numbers:

E 1.99:la-ur-01-3669
la-ur-01-3669

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Published through SciTech Connect.
01/01/2001.
"la-ur-01-3669"
Presented at the Institute of Nuclear Materials Management 42nd Annual Meeting, Indian Wells, California, July 15-19, 2001.
Polk, P. J.; Baker, M. C.; Harker, W. C.; Pelowitz, D. G.; Abhold, M. E.; Bourret, S. C.

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