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Title: Demonstration of LOTUS multiphysics BEPU analysis framework for LB-LOCA simulations

Journal Article · · Annals of Nuclear Energy (Oxford)

The LOCA Toolkit for U.S. light water reactors (LOTUS) currently under development at Idaho National Labs (INL) is a plug and play, multiphysics environment to be used in support of system level plant transient analysis. New proposed rule changes in LOCA safety regulations (10 CFR 50.46c) require the inclusion of cladding hydrogen content in the evaluation of equivalent cladding reacted (ECR) and peak cladding temperature (PCT). The potential for a future implementation of said rule change motivates the current development of a unique union of core design, system analysis, and fuel performance codes within a framework allowing for uncertainty quantification (UQ). A demonstration of LOTUS capabilities to address this potential need is performed with an integration of the core design code PHISICS, the fuel performance code FRAPCON, and the system analysis code RELAP5-3D. UQ is performed via Wilks’ method to compute the one sided 95/95 confidence values of the aforementioned safety metrics. Results demonstrate the benefits of the Multiphysics Best Estimate Plus Uncertainty (MP-BEPU) methodology and provide useful visualization of the limiting cases.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Energy Efficiency and Renewable Energy (EERE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1618429
Alternate ID(s):
OSTI ID: 1703572
Report Number(s):
INL-JOU-18-45131-Rev000; TRN: US2106816
Journal Information:
Annals of Nuclear Energy (Oxford), Vol. 122, Issue C; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 1 work
Citation information provided by
Web of Science

References (16)

Uncertainty quantification and sensitivity analysis with CASL Core Simulator VERA-CS journal September 2016
Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response journal August 2018
An Overview of Westinghouse Realistic Large Break LOCA Evaluation Model journal January 2008
MOOSE: A parallel computational framework for coupled systems of nonlinear equations journal October 2009
Statistical aspects of best estimate method—I journal June 2003
Advanced multiphysics coupling for LWR fuel performance analysis journal October 2015
Comparison of global sensitivity analysis methods – Application to fuel behavior modeling journal February 2016
High-fidelity multi-physics system TORT-TD/CTF/FRAPTRAN for light water reactor analysis journal October 2015
Potential Impacts of Modeling Full Reactor Cores Using Combined Fuel Performance and Thermal Hydraulics Codes journal May 2015
New Simulation Schemes and Capabilities for the PHISICS/RELAP5-3D Coupled Suite journal January 2016
An Overview of Computational Environments for Engineering
  • Sloan, Benjamin; McCorkle, Doug; Bryden, Kenneth
  • 51st AIAA Aerospace Sciences Meeting including the New Horizons Forum and Aerospace Exposition https://doi.org/10.2514/6.2013-285
conference January 2013
Comparison of the PHISICS/RELAP5-3D Ring and Block Model Results for Phase I of the OECD/NEA MHTGR-350 Benchmark journal January 2016
A generic semi-implicit coupling methodology for use in RELAP5-3D© journal January 2002
Determination of Sample Sizes for Setting Tolerance Limits journal March 1941
Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions journal November 2015
Multi-physics code system with improved feedback modeling journal July 2017