PUFF-III
Subtitle: a code for processing ENDF uncertainty data into multigroup covariance matrices
By: prepared by M.E. Dunn ; prepared for Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
Contributors: U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness.; Oak Ridge National Laboratory.
Publisher: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research; [Supt. of Docs., U.S. G.P.O., distributor]
Published: 2000
Place of publication: Washington, DC
Language: eng
Format: Microform
Number of pages: 94
Subjects: Cross sections (Nuclear physics) -- Computer programs; Nuclear reactors -- United States -- Shielding (Radiation) -- Computer programs; Radiation dosimetry -- Computer programs; Analysis of covariance -- Computer programs
Other titles: Code for processing ENDF uncertainty data into multigroup covariance matrices.
Notes: "Oak Ridge National Laboratory"--Cover.

Shipping list no.: 2000-0873-M.

"Date published: June 2000."

"NUREG/CR-6650."

"ORNL/TM-1999/235."

Includes bibliographical references (p. 69).

Technical.

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [2000]. 2 microfiches : negative.

W6479.