BWR Refill-Reflood Program: Task 4. 3 - Single Heated Bundle. Final report

Technical Report · Fri Apr 01 04:00:00 EST 1983

DOI:https://doi.org/10.2172/6210293· OSTI ID:6210293

Sutherland, W. A.; Barton, J. E.; Findlay, J. A.

Separate effects and system response tests conducted in the Single Heated Bundle (SHB) facility have produced data for evaluating: (a) low flow core spray heat transfer; (b) bundle bottom reflood heat transfer; (c) channel to bypass heat transfer; and (d) BWR refill-reflood controlling phenomena. These data support model development and qualification. Transient Loss of Coolant Accident (LOCA) experiments conducted in the SHB test facility have demonstrated that an adiabatic bundle system, using steam injection to simulate vaporization, simulates the thermal-hydraulic system response of a heated bundle system. These tests which were conducted by subjecting the adiabatic bundle and then an electrically heated bundle to the same LOCA transients, confirm the application of the adiabatic steam injection technique to a large-scale test facility.

• Research Organization: General Electric Co., San Jose, CA (USA). Nuclear Fuel and Special Projects Div.
• OSTI ID: 6210293
• Report Number(s): NUREG/CR-2001; EPRI-NP-2372; GEAP-24936; ON: DE83901796
• Country of Publication: United States
• Language: English

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