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Title: SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems

Abstract

New multigroup cross section libraries and associated covariance files that are optimized for the analysis of sodium-cooled fast reactors were generated with the AMPX tools distributed with the SCALE code system. These new libraries account for the fast neutron flux spectrum with sufficient resolution of resonances in the higher energy range to reproduce continuous-energy reference results and to provide the basis for sensitivity and uncertainty analyses of fast spectrum systems with the SCALE code system. The performance of the new libraries was investigated in terms of the eigenvalue, the neutron flux and reaction rates in criticality calculations, and the generation of group constants. A library using 302 energy groups and a fast neutron flux spectrum as the weighting function led to very good agreement with reference continuous-energy results. As a result, the performance of the new library was demonstrated in calculations of experiments from the International Criticality Safety Benchmark Evaluation Project handbook.

Authors:
ORCiD logo [1]; ORCiD logo [2];  [3];  [4]
+ Show Author Affiliations
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); École polytechnique fédérale de Lausanne (Switzerland)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany)
  4. École polytechnique fédérale de Lausanne (Switzerland)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1607257
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 140; Journal Issue: C; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; sodium-cooled fast reactor; SFR-UAM; SCALE; multigroup library

Citation Formats

Bostelmann, Friederike, Rearden, Bradley T., Zwermann, Winfried, and Pautz, Andreas. SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems. United States: N. p., 2019. Web. doi:10.1016/j.anucene.2019.107102.
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Bostelmann, Friederike, Rearden, Bradley T., Zwermann, Winfried, & Pautz, Andreas. SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems. United States. https://doi.org/10.1016/j.anucene.2019.107102
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Bostelmann, Friederike, Rearden, Bradley T., Zwermann, Winfried, and Pautz, Andreas. Thu . "SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems". United States. https://doi.org/10.1016/j.anucene.2019.107102. https://www.osti.gov/servlets/purl/1607257.
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@article{osti_1607257,
title = {SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems},
author = {Bostelmann, Friederike and Rearden, Bradley T. and Zwermann, Winfried and Pautz, Andreas},
abstractNote = {New multigroup cross section libraries and associated covariance files that are optimized for the analysis of sodium-cooled fast reactors were generated with the AMPX tools distributed with the SCALE code system. These new libraries account for the fast neutron flux spectrum with sufficient resolution of resonances in the higher energy range to reproduce continuous-energy reference results and to provide the basis for sensitivity and uncertainty analyses of fast spectrum systems with the SCALE code system. The performance of the new libraries was investigated in terms of the eigenvalue, the neutron flux and reaction rates in criticality calculations, and the generation of group constants. A library using 302 energy groups and a fast neutron flux spectrum as the weighting function led to very good agreement with reference continuous-energy results. As a result, the performance of the new library was demonstrated in calculations of experiments from the International Criticality Safety Benchmark Evaluation Project handbook.},
doi = {10.1016/j.anucene.2019.107102},
journal = {Annals of Nuclear Energy (Oxford)},
number = C,
volume = 140,
place = {United States},
year = {Thu Oct 17 00:00:00 EDT 2019},
month = {Thu Oct 17 00:00:00 EDT 2019}
}
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Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1016/j.anucene.2019.107102
Copyright Statement
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Figures / Tables:

Fig. 1 Fig. 1: Neutron flux of two volume-homogenized SFR fuel assemblies (MET1000: metallic fuel, MOX3600: oxide fuel) compared to a Light Water Reactor (LWR) pin cell spectrum: Weighting spectra of the multigroup libraries.
All figures and tables (38 total)
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Works referenced in this record:

Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques
journal, March 2004

  • Broadhead, B. L.; Rearden, B. T.; Hopper, C. M.
  • Nuclear Science and Engineering, Vol. 146, Issue 3
  • DOI: 10.13182/NSE03-2

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data
journal, December 2011

MC 2 -3: Multigroup Cross Section Generation Code for Fast Reactor Analysis
journal, June 2017

The Serpent Monte Carlo code: Status, development and applications in 2013
journal, August 2015

Implementation, capabilities, and benchmarking of Shift, a massively parallel Monte Carlo radiation transport code
journal, March 2016

  • Pandya, Tara M.; Johnson, Seth R.; Evans, Thomas M.
  • Journal of Computational Physics, Vol. 308
  • DOI: 10.1016/j.jcp.2015.12.037

SCALE Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations
journal, March 2016

  • Perfetti, Christopher M.; Rearden, Bradley T.; Martin, William R.
  • Nuclear Science and Engineering, Vol. 182, Issue 3
  • DOI: 10.13182/NSE15-12

Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core
journal, January 2017

Sensitivity and Uncertainty Analysis for Eigenvalue-Difference Responses
journal, January 2007

  • Williams, Mark L.
  • Nuclear Science and Engineering, Vol. 155, Issue 1
  • DOI: 10.13182/NSE06-11

A Statistical Sampling Method for Uncertainty Analysis with SCALE and XSUSA
journal, September 2013

  • Williams, M. L.; Ilas, G.; Jessee, M. A.
  • Nuclear Technology, Vol. 183, Issue 3
  • DOI: 10.13182/NT12-112
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    Figures / Tables found in this record:

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