Parametric Sensitivity Study on the Reflooding Models of the MARS Code Based on 6 × 6 Rod Bundle Test Results
Author:
Affiliation:
1. Korea Atomic Energy Research Institute, Thermal Hydraulics Safety Research Division 1045 Daedeokdaero, Yuseong, Daejeon, 305-353, Korea
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT10-A9445
Reference18 articles.
1. FLECHT SEASET PROGRAM, “PWR FLECHT SEASET Unblocked Bundle, Forced and Gravity Reflood Task Data Report,” Vols. 1 and 2. NUREG/CR-1532, EPRI NP-1459, WCAP-9699, Westinghouse Company (1980).
2. T. IGUCHI, “Study on Thermal Hydraulics During a PWR Reflood Phase,” JAERI-Research 98-54, Japan Atomic Energy Research Institute (1998).
3. Summary of CCTF test results - assessment of current safety evaluation analysis on reflood behavior during a LOCA in a PWR with cold-leg-injection-type ECCS
4. Large-scale multi-dimensional phenomena found in CCTF and SCTF experiments
5. UPTF experiment refined PWR LOCA thermal-hydraulic scenarios: conclusions from a full-scale experimental program
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2. Experimental observation of the droplet size change across a wet grid spacer in a 6×6 rod bundle;Nuclear Engineering and Design;2011-12
3. A separate effect test on the cooling behavior in a pressurized water reactor core under a low reflooding rate condition by using ATLAS and RELAP5/MOD3.3 code assessment;Annals of Nuclear Energy;2011-05
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