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Boiling water reactor uranium utilization improvement potential [electronic resource].

Published
Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1980.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 167 : digital, PDF file
Additional Creators
Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
This report documents the results of design and operational simulation studies to assess the potential for reduction of BWR uranium requirements. The impact of the improvements on separative work requirements and other fuel cycle requirements also were evaluated. The emphasis was on analysis of the improvement potential for once-through cycles, although plutonium recycle also was evaluated. The improvement potential was analyzed for several design alternatives including axial and radial natural uranium blankets, low-leakage refueling patterns, initial core enrichment distribution optimization, reinsert of initial core discharge fuel, preplanned end-of-cycle power coastdown and feedwater temperature reduction, increased discharge burnup, high enrichment discharge fuel rod reassembly and reinsert, lattice and fuel bundle design optimization, coolant density spectral shift with flow control, reduced burnable absorber residual, boric acid for cold shutdown, six-month subcycle refueling, and applications of a once-through thorium cycle design and plutonium recycle.
Report Numbers
E 1.99:ornl/sub-7537/15
ornl/sub-7537/15
Subject(s)
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Note
Published through SciTech Connect.
06/01/1980.
"ornl/sub-7537/15"
"DE82007498"
Tilley, R.M.; Townsend, D.B.; Wolters, R.A.; Wei, P.; Fennern, L.E.; Crowther, R.L.; Specker, S.R.; Savoia, P.J.
Funding Information
W-7405-ENG-26
View MARC record | catkey: 14802623