PUFF-III

a code for processing ENDF uncertainty data into multigroup covariance matrices

By M. E. Dunn

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Publish Date

2000

Publisher

U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,[Supt. of Docs., U.S. G.P.O., distributor]

Language

eng

Pages

Description:

subjects: Computer programs, Cross sections (Nuclear physics), Analysis of covariance, Radiation dosimetry, Nuclear reactors, Shielding (Radiation)

Places: United States