Annotated bibliography covering generation and use of evaluated cross section uncertainty files
Literature references related to definition, generation, and use of evaluated cross section uncertainty (variance-covariance) files are listed with comments intended primarily to guide the reader toward materials of immediate interest. Papers are also cited that cover covariance information for individual experiments and that relate to production and use of multigroup covariance matrices. Titles are divided among several major categories.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brookhaven National Lab. (BNL), Upton, NY (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5591174
- Report Number(s):
- BNL-NCS-51684; ON: DE83017884
- Country of Publication:
- United States
- Language:
- English
Similar Records
SENSIT: a cross-section and design sensitivity and uncertainty analysis code. [For CDC 7600]
SENSIT: a cross-section and design sensitivity and uncertainty analysis code. [In FORTRAN for CDC-7600, IBM 360]
PUFF-III: A Code for Processing ENDF Uncertainty Data Into Multigroup Covariance Matrices
Technical Report
·
Fri Aug 01 00:00:00 EDT 1980
·
OSTI ID:5591174
SENSIT: a cross-section and design sensitivity and uncertainty analysis code. [In FORTRAN for CDC-7600, IBM 360]
Conference
·
Tue Jan 01 00:00:00 EST 1980
·
OSTI ID:5591174
PUFF-III: A Code for Processing ENDF Uncertainty Data Into Multigroup Covariance Matrices
Technical Report
·
Thu Jun 01 00:00:00 EDT 2000
·
OSTI ID:5591174
Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
DATA COVARIANCES
BIBLIOGRAPHIES
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
CROSS SECTIONS
COMPUTER CALCULATIONS
COMPUTER CODES
DIFFERENTIAL CROSS SECTIONS
INTEGRAL CROSS SECTIONS
MATRICES
MULTIGROUP THEORY
DOCUMENT TYPES
NEUTRON TRANSPORT THEORY
TRANSPORT THEORY
651000* - Nuclear Physics
DATA COVARIANCES
BIBLIOGRAPHIES
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
CROSS SECTIONS
COMPUTER CALCULATIONS
COMPUTER CODES
DIFFERENTIAL CROSS SECTIONS
INTEGRAL CROSS SECTIONS
MATRICES
MULTIGROUP THEORY
DOCUMENT TYPES
NEUTRON TRANSPORT THEORY
TRANSPORT THEORY
651000* - Nuclear Physics