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Dunn, M. E.
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Dunn, M. E.
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Dunn, M. E.
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PUFF-III : a code for processing ENDF uncertainty data into multigroup covariance matrices /
by
Dunn
,
M
.
E
.
Published 2000
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2
POLIDENT, a module for generating continuous-energy cross sections from ENDF resonance data /
by
Dunn
,
M
.
E
.
Published 2000
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Related Subjects
Computer programs
Cross sections (Nuclear physics)
Analysis of covariance
Data processing
Neutron resonance
Nuclear reactions
Nuclear reactors
Radiation dosimetry
Shielding (Radiation)
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