FFTF RELATED STUDIES IN THE ORNL--LMFBR SHIELDING PROGRAM. Page: 1 of 55
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G P IO N A J l a
OAK RIDGE NATIONAL LABORATORY
UNION CARBIDE CORPORATION * NUCLEAR DIVISION
U.S. ATOMIC ENERGY COMMISSION
ORNL - TM- 3705
DATE - March 27, 1972
Neutron Physics Division
FFTF RELATED STUDIES IN THE ORNL-LMFBR SHIELDING PROGRAMt
F. R. Mynatt, C. E. Clifford, F. J. Muckenthaler, R. E. Maerker,
M. L. Gritzner, L. R. Williams, and J. L. Rathbun*
This paper documents an oral presentation given in the special
session on Fast Reactor Shielding Sponsored by the Shielding and
Dosimetry Division at the October 1971 meeting of the American
Nuclear Society in Miami, Florida. The progress to date on neutron
transport calculational studies of FFTF shielding design is presented,
including the analysis of supporting integral experiments. The
major FFTF shielding problems considered were the predictions of
(1) neutron dose rates above the reactor head and (2) neutron fluence
intensities at the core support grid plate.
tPresented at ANS Meeting, Miami Beach, Fla., Oct. 17, 1971.
Westinghouse Electric Co., Madison, Pa. 15663.
NOTICE This document contains information of a preliminary nature
and was prepared primarily for internal use at the Oak Ridge Notional
Laboratory. It is subject to revision or correction and therefore does
not represent a final report.
DISTRIBUTION OF THIS DOCUMENT IS U1LIM
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Mynatt, F.R.; Clifford, C.E.; Muckenthaler, F.J.; Maerker, R.E.; Gritzner, M.L.; Williams, L.R. et al. FFTF RELATED STUDIES IN THE ORNL--LMFBR SHIELDING PROGRAM., report, January 1, 1972; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc1030630/m1/1/: accessed January 22, 2019), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.