A CANDU multiple-channel thermosyphoning flow stability model
Creators
- 1. Atomic Energy of Canada Ltd., Sheridan Park, ON (Canada). CANDU Operations
- 2. Hydro-Quebec, Montreal, PQ (Canada)
- 3. New Brunswick Power, Lepreau (Canada)
Description
This paper describes an algebraic linear model (dubbed MMOSS for Model of Multiple-channel OScillationS) developed to explain and predict pass-to-pass out-of-phase oscillatory behaviour in a CANDU-type multiple-channel figure-of-eight loop under two-phase thermosyphoning conditions. MMOSS was developed for a figure-of-eight system of any number of channels. The system characteristic equation was derived from a linearization of the conservation equations for mass, momentum, and energy. MMOSS is a simple generalization of a previous model for a single-channel system. In this paper, the MMOSS characteristic equation is solved for a system of N identical channels. This simplification provides valuable physical insight and some reasonably accurate results. Furthermore, the simplification is not unrealistic because, in a multiple-channel system, a group or groups of channels are nearly similar. From the MMOSS characteristic function for the RD-14M facility under two-phase thermosyphoning conditions, a flow stability map is generated as a function of loop integrated void, secondary side pressure, and channel power. MMOSS predicts that the flow is stable above about 4 MPa secondary side pressure. At a given pressure below this pressure, the flow is unstable over a range of the void. This range is larger the lower the pressure. These predictions agree reasonably well with the results of the RD-14M experiments. (author) 11 refs., 5 figs
Additional details
Publishing Information
- Imprint Title
- Proceedings of the Canadian Nuclear Society 15. annual conference
- Imprint Pagination
- [1000 p.].
- Journal Page Range
- (v.1) [21 p.].
- ISSN
- 0227-1907
- Report number
- INIS-mf--14987(v.1,2)
Conference
- Title
- 15. annual conference of the Canadian Nuclear Society; 34. annual conference of the Canadian Nuclear Association.
- Dates
- 5-8 Jun 1994.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 28014290
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; LOSS OF COOLANT; M CODES; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY EXPERIMENTS; STABILITY; TEST FACILITIES; THERMOSYPHONS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; FLUID FLOW; HEAT TRANSFER; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SIMULATION; THERMAL REACTORS