Optimization of Thermal-Hydraulic Reactor System for SMRs via Data Assimilation and Uncertainty Quantification-Reference-Cited by-同舟云学术

Optimization of Thermal-Hydraulic Reactor System for SMRs via Data Assimilation and Uncertainty Quantification

Published:2013-03 Issue:3 Volume:173 Page:293-311
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Heo Jaeseok¹,Turinsky Paul J.¹,Doster J. Michael¹

Affiliation:

1. North Carolina State University, Department of Nuclear Engineering Raleigh, North Carolina 27695-7909

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE11-113

Reference16 articles.

1. M. D. CARELLI, “IRIS: Final Technical Progress Report,” STD-ES-03-40, Westinghouse Electric Company (Nov. 3, 2003).

2. H. SHEN, “Advanced Feedwater Control for Next Generation Nuclear Power Systems,” PhD Dissertation, North Carolina State University (2006).

3. J. M. DOSTER and P. J. TURINSKY, “Advanced Instrumentation and Control Methods for Small and Medium Reactors with IRIS Demonstration—Final Report Volume 2: IRIS Simulator Development and Measurement Sensitivity Analysis,” DE-FG07-07ID14895/UTNE/2011-4, University of Tennessee (May 2011).

4. Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology

5. Outline of the Uncertainty Methodology Based on Accuracy Extrapolation

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