Survey of prediction capabilities of three nuclear data libraries for a PWR application

Risto Vanhanen, Maria Pusa

Research output: Contribution to journalArticleScientificpeer-review

2 Citations (Scopus)


We survey prediction capabilities of ENDF/B-VII.1, JEFF-3.2 and JENDL-4.0u nuclear data libraries (NDLs) for the application of generating two-group homogenized assembly constants for a steady state diffusion model in the context of UAM-LWR (Uncertainty Analysis in Best-Estimate Modeling for Design, Operation and Safety Analysis of LWRs) Benchmark. We consider two different fuel assembly test cases representing a PWR. State of uncertainty quantification in each NDLs is presented for the application. We expect small differences between the NDLs due to the use of expert judgment in the evaluation processes, and identify several order-of-magnitude differences between the NDLs for significant contributors to uncertainty. We also quantify the contribution from cross-material correlations to the uncertainties.
Original languageEnglish
Pages (from-to)408-421
JournalAnnals of Nuclear Energy
Publication statusPublished - 2015
MoE publication typeA1 Journal article-refereed


  • rediction capability
  • uncertainty analysis
  • ENDF/B-VII.1
  • JEFF-3.2
  • JENDL-4.0u
  • cross-material covariances


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