Boiling Water Reactor-full Length Emergency Core Cooling Heat Transfer (BWR- FLECHT) Tests Project. Final Report on Atmospheric Pressure Stainless Steel Experiments PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Stainless steel-clad bundle experiments at atmospheric pressure were conducted as a part of the Boiling Water Reactor -- Full Length Emergency Cooling Heat Transfer (BWR-FLECHT) Tests Project. This project was coordinated by Aerojet Nuclear Company and performed by the General Electric Company for the Atomic Energy Commission as a pant of the Water Reactor Safety Program. The BWR.- FLECHT project was designed to investigate the thermal and hydraulic phenomena associated with the emergency core cooling (ECC) injection portion of a loss-of- coolant accident (LOCA) in a boiling water reactor (BWR). Twenty-three bottom flooding experiments, twenty-seven top spray experiments, and eight connbined spraying and flooding experiments were penformed on two rod bundles containing stainless steel-clad heaters as fuel pin simulators. The ranges of experimental conditions were the following. Bundle initial power ranged from 25 to 390 kW, dooding rates ranged from 0.63 to 6.05 in./sec, spray rates ranged from 1.0 to 5.0 gpm, and bundle initial maximunn temperatures ranged from 320 to 2150 deg F. The major parameters and results of these tests are discussed, and comments are presented regarding the effect of variations in the parameters on the heat transfer coefficients and bundle thermal response. (auth).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Stainless steel-clad bundle experiments at atmospheric pressure were conducted as a part of the Boiling Water Reactor -- Full Length Emergency Cooling Heat Transfer (BWR-FLECHT) Tests Project. This project was coordinated by Aerojet Nuclear Company and performed by the General Electric Company for the Atomic Energy Commission as a pant of the Water Reactor Safety Program. The BWR.- FLECHT project was designed to investigate the thermal and hydraulic phenomena associated with the emergency core cooling (ECC) injection portion of a loss-of- coolant accident (LOCA) in a boiling water reactor (BWR). Twenty-three bottom flooding experiments, twenty-seven top spray experiments, and eight connbined spraying and flooding experiments were penformed on two rod bundles containing stainless steel-clad heaters as fuel pin simulators. The ranges of experimental conditions were the following. Bundle initial power ranged from 25 to 390 kW, dooding rates ranged from 0.63 to 6.05 in./sec, spray rates ranged from 1.0 to 5.0 gpm, and bundle initial maximunn temperatures ranged from 320 to 2150 deg F. The major parameters and results of these tests are discussed, and comments are presented regarding the effect of variations in the parameters on the heat transfer coefficients and bundle thermal response. (auth).
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Author: S. G. Forbes
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Author: J. C. Haire
Author: United States. Superintendent of Documents
Author: Sadik Kakaç