Scaling, Passive Systems, and the AP-1000

References

• F. D’AURIA, N. AKSAN, and Y. HASSAN, “Nuclear Thermal-Hydraulics: What Is It?,” J. Nucl. Eng. Des., 354, 110246 (2019); paper (PI-2).
   Web of Science ®Google Scholar
• F. D’AURIA and Y. HASSAN, “Challenges and Concerns for Development of Nuclear Thermal-Hydraulics,” J. Nucl. Eng. Des., 375, 111074 (2021).
   Web of Science ®Google Scholar
• F. D’AURIA, “Passive Systems and Nuclear Thermal Hydraulics,” J. Nucl. Eng. Des., 385, 111513 (2021).
   Web of Science ®Google Scholar
• D. BESTION et al., “The OECD /NEA/CSNI Scaling State of the Art Report—The S-SOAR,” NEA/CSNI/R(2016)14, p. 1, Organisation for Economic Co-operation and Development/Nuclear Energy Agency, Committee on the Safety of Nuclear Installations (Mar. 2017).
   Google Scholar
• F. D’AURIA et al., “Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation,” IAEA Safety Report Series, SRS No 52, p. 1, International Atomic Energy Agency (2008).
   Google Scholar
• F. D’AURIA et al., “Three Mile Island Unit 1 Main Steam Line Break Three Dimensional Neutronics/Thermal-Hydraulics Analysis: Application of Different Coupled Codes,” Nucl. Technol., 142, 1, 180 (2003); https://doi.org/10.13182/NT03-A3383.
   Web of Science ®Google Scholar
• F. D’AURIA, “An Old Issue and a New Challenge for Nuclear Reactor Safety,” J. Front. Energy, 15, 854 (2021); https://doi.org/10.1007/s11708-021-0729-0.
   Web of Science ®Google Scholar
• F. D’AURIA et al., “The Simulation of I & C in Accident Analyses of Nuclear Power Plants,” J. Nucl. Eng. Des., 250, 656 (2012); https://doi.org/10.1016/j.nucengdes.2012.04.022.
   Web of Science ®Google Scholar
• F. D’AURIA, “Best Estimate Plus Uncertainty (BEPU): Status and Perspective,” J. Nucl. Eng. Des., 352, 110190 (2019).
   Web of Science ®Google Scholar
• F. D’AURIA et al., “Pressurized Heavy Water Reactors—Atucha II,” Vol. 8, J. RIZNIC, Ed., Elsevier (Oct. 2021).
   Google Scholar
• F. D’AURIA, “Thermal Hydraulics in Water-Cooled Nuclear Reactors,” Elsevier, Woodhead Publishing (June 2017).
   Google Scholar
• F. D’AURIA and G. M. GALASSI, “Scaling in Nuclear Reactor System Thermal-Hydraulics,” J. Nucl. Eng. Des., 240, 3267 (2010); https://doi.org/10.1016/j.nucengdes.2010.06.010.
   Web of Science ®Google Scholar
• W. AMBROSINI, R. BOVALINI, and F. D’AURIA, “Evaluation of Accuracy of Thermal-Hydraulics Codes Calculations,” J. Energia Nucl., 7, 2 (1990).
   Google Scholar
• S. BANERJEE et al., “Scaling in the Safety of Next Generation Reactors,” Nucl. Eng. Des., 186, 111 (1998); https://doi.org/10.1016/S0029-5493(98)00219-2.
   Web of Science ®Google Scholar
• F. D’AURIA, H. KARWAT, and M. MAZZINI, “Planning of Counterpart Tests in LWR Experimental Simulators,” Proc. ANS National Heat Transfer Conf., Houston, Texas (1988).
   Google Scholar
• B. E. BOYACK et al., “Quantifying Reactor Safety Margins—Application of Code Scaling, Applicability and Uncertainty Evaluation Methodology to a Large Break, Loss-of-Coolant Accident,” NUREG/CR-5249, U.S. Nuclear Regulatory Commission (1989).
   Google Scholar
• F. D’AURIA, N. DEBRECIN, and G. M. GALASSI, “Outline of the Uncertainty Methodology Based on Accuracy Extrapolation (UMAE),” J. Nucl. Technol., 109, 1, 21 (1995); https://doi.org/10.13182/NT109-21.
   Web of Science ®Google Scholar
• F. D’AURIA and W. GIANNOTTI, “Development of Code with Capability of Internal Assessment of Uncertainty,” Nucl. Technol., 131, 1, 159 (2000); https://doi.org/10.13182/NT00-5.
   Web of Science ®Google Scholar
• F. D’AURIA and G. M. GALASSI, “Methodology for the Evaluation of the Reliability of Passive Systems,” DIMNP-NT 420 (00)-Rev.1, University of Pisa (2000).
   Google Scholar
• J. JAFARI et al., “Reliability Evaluation of a Natural Circulation System,” J. Nucl. Eng. Des., 224, 79 (2003); https://doi.org/10.1016/S0029-5493(03)00105-5.
   Web of Science ®Google Scholar
• M. MARQUES et al., “Methodology for the Reliability Evaluation of a Passive System and Its Integration into a Probabilistic Safety Assessments,” J. Nucl. Eng. Des., 235, 2612 (2005); https://doi.org/10.1016/j.nucengdes.2005.06.008.
   Web of Science ®Google Scholar
• C. HERER et al., “SOAR on Reliability of Thermal-Hydraulic Passive Systems (SOAR-RPS),” Draft Rev.06, F. D’AURIA, Ed., presented at the Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations 4th Passive Systems Workshop, Tirrenia (Pisa), Italy, Dec. 11–13, 2019.
   Google Scholar
• W. T. SHA et al., “Analysis of Large-Scale Tests for AP-600 Passive Containment Cooling System,” J. Nucl. Eng. Des., 232, 197 (2004); https://doi.org/10.1016/j.nucengdes.2004.05.003.
   Web of Science ®Google Scholar
• K. C. ABEL et al., “OSU APEX-1000 Test Facility Description,” OSU-APEX-03002 (Rev. 0), U.S. Department of Energy (2003).
   Google Scholar
• K. B. WELTER et al., “APEX-AP1000 Confirmatory Testing To Support AP1000 Design Certification,” NUREG 1826, U.S. Nuclear Regulatory Commission (2005).
   Google Scholar
• C. SMITH, “Information on the Advanced Plant Experiment (APEX) Test Facility,” INL/EXT-15-35316, Idaho National Laboratory (2015).
   Google Scholar
• “Final Safety Evaluation Report Related to Certification of the AP1000 Standard Plant Design Docket No. 52-006,” NUREG 1793, U.S. Nuclear Regulatory Commission (2005).
   Google Scholar
• “Status Report 81—Advanced Passive PWR (AP 1000),” Westinghouse (2011).
   Google Scholar
• S. A. OLATUBOSUN, A. AYODEJI, and M. A. AMIDU, “Safety Assessment of AP1000: Common Transients, Analysis Codes and Research Gaps,” J. Nucl. Eng. Des., 375, 111100 (2021); https://doi.org/10.1016/j.nucengdes.2021.111100.
   Web of Science ®Google Scholar
• F. D’AURIA, N. DEBRECIN, and H. GLAESER, “Strengthening Nuclear Reactor Safety and Analysis,” J. Nucl. Eng. Des., 324, 209 (2017); https://doi.org/10.1016/j.nucengdes.2017.09.008.
   Web of Science ®Google Scholar
• F. D’AURIA, “Panelist Notes, Invited at Panel: Reliability of Passive Systems,” presented at the 17th Int. Topl. Mtg. Nuclear Reactor Thermal-Hydraulics (NURETH-17), Xi’an, China, September 3–9, 2017.
   Google Scholar