Estimated uncertainties in nuclear data: an approach. [ENDF/B]

Conference · Wed Oct 01 04:00:00 EDT 1975 · Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States)

OSTI ID:7365018

Perey, F G

The need to communicate estimated uncertainties in evaluated nuclear data to be used in the assessment of their adequacy in applications has been recognized in the ENDF/B system. Starting with ENDF/B-IV, the data files contain formatted data describing the estimated covariances of some of the microscopic cross sections in such a form that they can be processed by computer codes to generate covariance matrices of quantities used in solving neutron transport problems such as group cross sections. The basic concepts behind the representation of such quantities are described and the work done so far in the representation and manipulation of such quantities is discussed. Problem areas not yet addressed in ENDF/B-IV but under study are discussed. (auth)

• Research Organization: Oak Ridge National Lab., TN
• OSTI ID: 7365018
• Conference Information: Journal Name: Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States) Journal Volume: 425
• Country of Publication: United States
• Language: English

Related Subjects

651000* -- Nuclear Physics
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
CROSS SECTIONS
ERRORS
HADRON REACTIONS
NEUTRON REACTIONS
NEUTRON TRANSPORT THEORY
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
TRANSPORT THEORY