Nuclear Power Plant Component Flooding Fragility Research

Technical Report · Sun Apr 01 00:00:00 EDT 2018

DOI:https://doi.org/10.2172/1467486· OSTI ID:1467486

Pope, C. L. ^[1]; Savage, B. ^[1]; Jash, S. ^[1]; Johnson, B. ^[1]; Muchmore, C. ^[1]; Nichols, L. ^[1]; Ryan, E. ^[1]; Suresh, S. ^[1]; Tahhan, A. ^[1]; Tuladhar, R. ^[1]; Wells, A. ^[1]; Smith, C. L. ^[2]

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1. Idaho State Univ., Pocatello, ID (United States)
2. Idaho National Lab. (INL), Idaho Falls, ID (United States)

This report describes progress on Nuclear Power Plant component flooding fragility research conducted at the Component Flooding Evaluation Laboratory (CFEL). The progress includes additional steering committee membership and invitations, performance improvements to the Portal Evaluation Tank (PET), PET based experiments using industrial steel doors, pipe rupture spray pattern characterization, coupling the smoothed particle hydrodynamics (SPH) code Neutrino and the Idaho National Laboratory (INL) developed Risk Analysis Virtual Environment (RAVEN), continued development of component fragility mathematical models, and wave impact simulation device development, testing, and analysis.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1467486
• Report Number(s): INL/EXT-18-45247-Rev000; TRN: US1902752
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
NUCLEAR POWER PLANTS
HYDRODYNAMICS
RISK ASSESSMENT
risk
safety
flooding
fragility