The analysis of bearing-pad t pressure-tube contact heat transfer experiments
Creators
- 1. Atomic Energy of Canada Limited, Pinawa, MB (Canada)
Description
An experimental program was established to study the influence of hot bearing pads on temperature transients of a ballooning pressure tube under postulated loss-of-coolant accident conditions in a CANDU. Twelve experiments were conducted in steam and Ar/O2 environments. Measured temperature and power transients from the experimental program were used with the mulitpurpose code CATHENA Mod-3.4/Rev 7 to infer the contact heat transfer coefficient between the bearing pad and the pressure tube. The empirically derived contact conductances are of special interest in the safety analysis of CANDU reactors. The contact heat transfer coefficients reached a maximum when the pressure-tube temperature was between 400 and 500 deg C beneath the bearing pads. The maximum value of contact heat transfer coefficient, calculated from experiments conducted in Ar/O2 environments, ranged from 1.1 to 1.5 kW/(m2 · K). The calculated contact heat transfer coefficients decreased to a negligible value (< 0.1 kW/(m2 · K)) in all experiments once the pressure-tube temperature exceed ∼ 630 deg C. This drop in heat transfer coefficient was due to localized deformation of the pressure tube beneath the bearing pads caused by the localized hot spot and the internal pressure-tube pressure. This deformation resulted in deteriorating conformity, between the pressure tube and the bearing pad, as evidenced by a decrease in the pressure-tube heatup rate and a coincident increase in the bearing-pad heatup rate. This paper summarizes the modeling methodology and analysis of results for the large-scale Integrated Bearing-Pad to Pressure-Tube Contact Heat Transfer experimental program. The work described in this paper was largely funded by the CANDU Owners Group (COG). (author)
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30032430.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the seventeenth annual Canadian Nuclear Society conference
- Imprint Pagination
- 820 p.
- Journal Page Range
- v. 2 [16 p.]
- Report number
- INIS-CA--0066(v.1,2)
Conference
- Title
- 17. annual Canadian Nuclear Society conference
- Dates
- 9-12 Jun 1996
- Place
- Fredericton, NB (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 30032430
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BEARINGS; C CODES; CANDU TYPE REACTORS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; LOSS OF COOLANT; PRESSURE TUBES; SAFETY ANALYSIS; TEMPERATURE MONITORING; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; MONITORING; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; TUBES
Optional Information
- Notes
- 11 refs., 2 tabs., 5 figs.