Covariance Testing Progress for ENDF/B-VIII.1β1 at ORNL [Slides]

Conference · Thu Apr 27 04:00:00 EDT 2023

DOI:https://doi.org/10.2172/1993965· OSTI ID:1993965

Marshall, B. J. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

This presentation touched on how data-induced uncertainty significantly increased for thermal ²³⁵U-fueled systems. And how ²³⁹Pu covariance changes are worrying. Additionally discussed is how ¹⁰³Rh is the only significant important fission product change. The Impact of ENDF/B-VIII.1β1 on burnup credit similarity assessments is similar to ENDF/B-VII.1 data.

• 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: 1993965
• Report Number(s): 193809
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
Benchmarks
Changes
Conclusions
Data-Induced Uncertainty
Nuclear Criticality Safety Program (NCSP)
VALID