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.2018.03.023Additional 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50082162
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- DEPARTURE NUCLEATE BOILING; FUEL CYCLE; IDAHO NATIONAL LABORATORY; LOSS OF COOLANT; NEUTRON TRANSPORT; NONLINEAR PROBLEMS; PERFORMANCE; PWR TYPE REACTORS; SENSITIVITY ANALYSIS; SIMULATION; TEMPERATURE MONITORING; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; BOILING; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; MONITORING; NATIONAL ORGANIZATIONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEATE BOILING; PHASE TRANSFORMATIONS; POWER REACTORS; RADIATION TRANSPORT; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; US DOE; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- © 2018 Elsevier B.V. All rights reserved.