The response of ex-core neutron detectors to large- and small-break loss-of-coolant accidents in pressurized water reactors

Journal Article · Sun Dec 01 04:00:00 EST 1991 · Nuclear Technology; (United States)

OSTI ID:5478236

Okyere, E W ^[1]; Baratta, A J; Jester, W A ^[2]

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1. City Univ. of New York, Staten Island, NY (US)
2. Pennsylvania State Univ., University Park, PA (United States). Dept. of Nuclear Engineering

This paper reports on a variety of water level measurement systems that are proposed to resolve the problem of reactor vessel level measurement. Two such systems, the heated thermocouple and the multiple differential pressure cell system, are used commercially. A third system based on ex-core neutron detectors was tested at the Pennsylvania State University Breazeale nuclear reactor facility and at the Idaho National Engineering Laboratory Loss-of-Fluid Test Facility. Results of these tests show that such a system is sensitive to both large- and small-break loss-of-coolant accidents and to voiding in the upper plenum of the vessel.

• OSTI ID: 5478236
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 96:3; ISSN 0029-5450; ISSN NUTYB
• Country of Publication: United States
• Language: English

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