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Development and Application of a Data-Driven Methodology for Validation of Risk-Informed Safety Margin Characterization Models

Technical Report ·
DOI:https://doi.org/10.2172/1776813· OSTI ID:1776813
 [1];  [2];  [2];  [2];  [2];  [3];  [4];  [5];  [6];  [7];  [8];  [9];  [9];  [9];  [10]
  1. North Carolina State Univ., Raleigh, NC (United States); Department of Nuclear Engineering, North Carolina State University
  2. North Carolina State Univ., Raleigh, NC (United States)
  3. Purdue Univ., West Lafayette, IN (United States)
  4. Univ. of Michigan, Ann Arbor, MI (United States)
  5. George Washington Univ., Washington, DC (United States)
  6. Zachry Nuclear Engineering, Idaho Falls, ID (United States)
  7. R.T. Sewell Associates, Louisville, Co (United States)
  8. Centroid PIC, Inc., Los Angeles, CA (United States)
  9. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  10. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
+ Show Author Affiliations

The document is the Final Technical Progress Report for the Nuclear Energy University Program’s Integrated Research Project (IRP) on “Development and Application of a Data-Driven Methodology for Validation of Risk-Informed Safety Margin Characterization Models” that supports the LWR Sustainability Program’s RISMC R&D Pathway. The project goal is to develop and demonstrate a data-driven methodology for validation of advanced computer models used in nuclear power plant safety analysis. Specifically, the advanced computer models are those in the toolkit developed to support risk-informed safety margin characterization (RISMC), an integrated deterministic/probabilistic safety analysis methodology developed in the Department of Energy’s Light Water Reactor Sustainability (LWR-S) program. The report reflects the progress made towards the project’s stated goal by contributions by researchers and graduate students from universities, with support from researchers from national laboratories and industry companies. The project organization, effort coordination and technical implementation are summarized, followed by discussion of main findings, issues, and path forward. Selected chapters provide a more detailed description of tasks, approaches and respective findings and recommendations. Noteworthy are contributions that serve as guidelines for methodology development. It is also noted that this report is complemented by other milestone reports (as stand-alone deliverables) that provide detailed discussion of the technical developments. The project results have been documented in a number (12) dissertations and these, 50+ peer-reviewed publications in technical journals and conference proceedings.

Research Organization:
North Carolina State Univ., Raleigh, NC (United States); Purdue Univ., West Lafayette, IN (United States); Univ. of Michigan, Ann Arbor, MI (United States); George Washington Univ., Washington, DC (United States); Zachry Nuclear Engineering, Idaho Falls, ID (United States); R.T. Sewell Associates, Louisville, Co (United States); Centroid PIC, Inc., Los Angeles, CA (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)
DOE Contract Number:
NE0008530
OSTI ID:
1776813
Report Number(s):
IRP--16-10918
Country of Publication:
United States
Language:
English

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42 ENGINEERING
97 MATHEMATICS AND COMPUTING
computational fluid dynamics
data-driven methodology
risk-informed safety margin
system thermal-hydraulics
validation