Published 2010 | Version v1
Book

Comparison of uncertainty quantification methods for fast reactor neutronics - 343

  • 1. Idaho National Laboratory, Idaho Falls, ID (United States)
  • 2. Sandia National Laboratories, Albuquerque, NM (United States)

Description

This paper describes a comparative study of two Uncertainty Quantification (UQ) techniques for reactor neutronics analysis. Adjoint- and sampling-based uncertainty quantification approaches are applied to a simplified model of a sodium-cooled fast reactor to evaluate uncertainty in four integral parameters (void reactivity, Doppler reactivity, Keff, and control rod reactivity). Results obtained with the two UQ methodologies are compared and discussed. This preliminary work, performed in a well-studied field like neutronics, will inform sensitivity and uncertainty method selection for future calculations in other disciplines like coupled neutronics/thermo-hydraulics. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, Illinois (United States)
ISBN
978-0-89448-079-9
Imprint Pagination
12 p.

Conference

Title
International Conference on Advances in Reactor physics to Power the Nuclear Renaissance
Acronym
PHYSOR 2010
Dates
9-14 May 2010
Place
Pittsburgh, PA (United States)

Optional Information

Notes
10 refs.