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

Risto Vanhanen, Maria Pusa

Research output: Contribution to journalArticleScientificpeer-review

1 Citation (Scopus)

Abstract

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
Volume83
DOIs
Publication statusPublished - 2015
MoE publication typeA1 Journal article-refereed

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Uncertainty analysis
Uncertainty

Keywords

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

Cite this

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title = "Survey of prediction capabilities of three nuclear data libraries for a PWR application",
abstract = "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.",
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language = "English",
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}

Survey of prediction capabilities of three nuclear data libraries for a PWR application. / Vanhanen, Risto; Pusa, Maria.

In: Annals of Nuclear Energy, Vol. 83, 2015, p. 408-421.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Survey of prediction capabilities of three nuclear data libraries for a PWR application

AU - Vanhanen, Risto

AU - Pusa, Maria

PY - 2015

Y1 - 2015

N2 - 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.

AB - 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.

KW - rediction capability

KW - uncertainty analysis

KW - ENDF/B-VII.1

KW - JEFF-3.2

KW - JENDL-4.0u

KW - cross-material covariances

U2 - 10.1016/j.anucene.2015.03.044

DO - 10.1016/j.anucene.2015.03.044

M3 - Article

VL - 83

SP - 408

EP - 421

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

SN - 0306-4549

ER -