Improving Limit Surface Search Algorithms in RAVEN Using Acceleration Schemes: Level II Milestone
The RAVEN code is becoming a comprehensive tool to perform Probabilistic Risk Assessment (PRA); Uncertainty Quantification (UQ) and Propagation; and Verification and Validation (V&V). The RAVEN code is being developed to support the RiskInformed Safety Margin Characterization (RISMC) pathway by developing an advanced set of methodologies and algorithms for use in advanced risk analysis. The RISMC approach uses system simulator codes applied to stochastic analysis tools. The fundamental idea behind this coupling approach to perturb (by employing sampling strategies) timing and sequencing of events, internal parameters of the system codes (i.e., uncertain parameters of the physics model) and initial conditions to estimate values ranges and associated probabilities of figures of merit of interest for engineering and safety (e.g. core damage probability, etc.). This approach applied to complex systems such as nuclear power plants requires performing a series of computationally expensive simulation runs. The large computational burden is caused by the large set of (uncertain) parameters characterizing those systems. Consequently, exploring the uncertain/parametric domain, with a good level of confidence, is generally not affordable, considering the limited computational resources that are currently available. In addition, the recent tendency to develop newer tools, characterized by higher accuracy and larger computational resources (ifmore »
 Authors:

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 Idaho National Laboratory (INL), Idaho Falls, ID (United States)
 Publication Date:
 OSTI Identifier:
 1244620
 Report Number(s):
 INL/EXT1536100
TRN: US1601048
 DOE Contract Number:
 AC0705ID14517
 Resource Type:
 Technical Report
 Research Org:
 Idaho National Laboratory (INL), Idaho Falls, ID (United States)
 Sponsoring Org:
 USDOE Office of Nuclear Energy (NE)
 Country of Publication:
 United States
 Language:
 English
 Subject:
 97 MATHEMATICS AND COMPUTING; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; R CODES; NUCLEAR POWER PLANTS; MATHEMATICAL MANIFOLDS; ALGORITHMS; MATHEMATICAL SPACE; SAFETY MARGINS; RISK ASSESSMENT; FAILURES; SAMPLING; COMPARATIVE EVALUATIONS; PROBABILISTIC ESTIMATION; REACTOR SAFETY; PERFORMANCE; PROBABILITY; SIMULATION; VALIDATION; STOCHASTIC PROCESSES; ACCURACY; DAMAGE; REACTOR CORES; RELIABILITY; VERIFICATION Limit Surface; Mathematics; PRA; Reliability Surface; Uncertainty Quantification
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