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Approximate Techniques for Representing Nuclear Data Uncertainties

Conference ·
OSTI ID:958811
 [1];  [1];  [1];  [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
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Computational tools are available to utilize sensitivity and uncertainty (S/U) methods for a wide variety of applications in reactor analysis and criticality safety. S/U analysis generally requires knowledge of the underlying uncertainties in evaluated nuclear data, as expressed by covariance matrices; however, only a few nuclides currently have covariance information available in ENDF/B-VII. Recently new covariance evaluations have become available for several important nuclides, but a complete set of uncertainties for all materials needed in nuclear applications is unlikely to be available for several years at least. Therefore, if the potential power of S/U techniques is to be realized for near-term projects in advanced reactor design and criticality safety analysis, it is necessary to establish procedures for generating approximate covariance data. This paper discusses an approach to create applications-oriented covariance data by applying integral uncertainties to differential data within the corresponding energy range.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
958811
Country of Publication:
United States
Language:
English

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Related Subjects

43 PARTICLE ACCELERATORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
ACCELERATORS
Advanced Reactor Design
CRITICALITY
Criticality Safety
Criticality Safety Analysis
DESIGN
ENERGY RANGE
ISOTOPES
MATRICES
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
Nuclear Data
Reactor Analysis
SAFETY
SAFETY ANALYSIS
SENSITIVITY
Sensitivity and Uncertainty (S/U)