PARAMETER IDENTIFICATION IN NUCLEAR REACTOR SYSTEMS. Page: 3 of 95
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ANL-7967
LMFBR Safety (UC-79p)ARGONNE NATIONAL LABORATORY
9700 South Cass Avenue
Argonne, Illinois 60439
PARAMETER IDENTIFICATION IN
NUCLEAR REACTOR SYSTEMS
by
William Stanley Roman
Reactor Analysis and Safety DivisionBased on a dissertation submitted to
the School of Engineering and Applied Science
University of Virginia
in partial fulfillment of the requirements
for the degree of
Doctor of Philosophy
in the field of Nuclear Engineering
NOTICE
This report was prepared as an account of work
sponsored by the United States Government. Neither
the United States nor the United States Atomic Energy
Commission, nor any of their employees, nor any of
their contractors, subcontractors, or their employees,
makes any warranty, express or implied, or assumes any
legal liability or responsibility for the accuracy, com-
pleteness or usefulness of any information, apparatus,
product or process disclosed, or represents that its use
would not infringe privately owned rights.September 1972
4ISTR MBUTION Of THIS D BCJ W2 T IS 1 7% T-
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Roman, W. S. PARAMETER IDENTIFICATION IN NUCLEAR REACTOR SYSTEMS., report, January 1, 1972; Illinois. (https://digital.library.unt.edu/ark:/67531/metadc1029284/m1/3/: accessed April 24, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.