PUFF-III : a code for processing ENDF uncertainty data into multigroup covariance matrices /

Bibliographic Details
Main Author: Dunn, M. E.
Corporate Authors: U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness, Oak Ridge National Laboratory
Format: Government Document Microform Book
Language:English
Published: Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research : 2000.
Subjects:

MARC

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100 1 |a Dunn, M. E. 
245 1 0 |a PUFF-III :  |b a code for processing ENDF uncertainty data into multigroup covariance matrices /  |c prepared by M.E. Dunn ; prepared for Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. 
246 3 0 |a Code for processing ENDF uncertainty data into multigroup covariance matrices 
264 1 |a Washington, DC :  |b U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research :  |c 2000. 
264 2 |a Washington, DC :  |b [Supt. of Docs., U.S. G.P.O., distributor], 
300 |a xi, 94 pages :  |b illustrations ;  |c 28 cm. 
336 |a text  |b txt  |2 rdacontent 
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500 |a Shipping List #: 2000-0873-M 
500 |a Shipping List Date: 09/25/2000 
513 |a Technical. 
500 |a "Oak Ridge National Laboratory"--Cover. 
500 |a Shipping list number: 2000-0873-M. 
500 |a "Date published: June 2000." 
504 |a Includes bibliographical references (page 69). 
500 |a "NUREG/CR-6650." 
500 |a "ORNL/TM-1999/235." 
536 |c W6479. 
533 |a Microfiche.  |b [Washington, D.C.] :  |c Supt. of Docs., U.S. G.P.O.,  |d [2000].  |e 2 microfiches : negative. 
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650 0 |a Cross sections (Nuclear physics)  |x Computer programs. 
650 0 |a Nuclear reactors  |z United States  |x Shielding (Radiation)  |x Computer programs. 
650 0 |a Radiation dosimetry  |x Computer programs. 
650 0 |a Analysis of covariance  |x Computer programs. 
710 2 |a U.S. Nuclear Regulatory Commission.  |b Division of Systems Analysis and Regulatory Effectiveness. 
710 2 |a Oak Ridge National Laboratory. 
999 |a MARS 
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