Published June 2018 | Version v1
Journal article

Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations

  • 1. Department of Mechanical and Aerospace Engineering, Utah State University, Old Main Hill, Logan, UT 84322 (United States)
  • 2. Idaho National Laboratory, 2525 Fremont Ave., Idaho Falls, ID 83415-3870 (United States)
  • 3. Department of Mechanical Engineering & Materials Science, University of Pittsburgh, 3700 O'Hara Street, Pittsburgh, PA 15261 (United States)

Description

Highlights: • Multiphysics integration of VERA-CS and BISON codes. • UQ of safety and performance figures of merit. • SA using regression, variance, and moment independent measures. - Abstract: Uncertainty quantification (UQ) and sensitivity analyses (SA) are performed for coupled simulations between VERA-CS, a coupled pin resolved neutron transport and subchannel thermal hydraulics code, and the fuel performance code BISON. The interface between VERA-CS and BISON is performed in a multiphysics environment known as the LOCA Toolkit for U.S. light water reactors (LOTUS) currently under development at Idaho National Laboratory (INL). A focus is placed on using a variety of SA measures, including two regression based (Pearson and Spearman), one variance based (Sobol indices), and three moment independent measures (Delta moment independent measures with L1, L2, and L norms). The problem under inspection is a single assembly depletion case for three fuel cycles. The figures of merit are the minimum departure from nucleate boiling ratio (MDNBR), maximum fuel centerline temperature (MFCT), and gap conductance at peak power (GCPP). SA results show MDNBR to be linear with consistent rankings throughout the fuel cycles. MFCT is linear, but with a change in rankings at the switch from open gap to closed gap models. GCPP is nonlinear at intermediate states that coincide with the onset of contact between fuel and cladding. These nonlinear states allow for the showcasing of higher order SA measures over first order methods.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2018.03.023

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2018.03.023;
PII
S0029549318302942;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
332
Journal Page Range
p. 186-201
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Notes
© 2018 Elsevier B.V. All rights reserved.