Thermosyphoning model and experimental verification with RD-14 tests
Creators
- 1. Energie et Analyses du Quebec Ltee., Montreal, PQ (Canada)
- 2. Ontario Hydro, Toronto, ON (Canada)
Description
This paper presents the work that has been undertaken in order to develop an understanding of the various phenomena that occur during thermosyphoning in a CANDU geometry. The test performed in the experimental loop RD-14 have been used to verify and further develop a computer code based on basic physical processes known to happen in the horizontal core, the feeders and the steam generators. The particular geometry of the loop has been used for verification purposes. It has been found that the location of the heat losses was of some importance in the timing of the phenomena. The major finding lies in the steam generator behaviour analysis where it has been concluded that the steam generator's parallel channels (U tubes) do have a series of independent patterns that affect the overall thermosyphoning flow of the loop. 6 refs., 10 figs
Additional details
Publishing Information
- ISBN
- 0-919784-31-3
- Imprint Title
- Canadian Nuclear Society/American Nuclear Society 4. international conference on simulation methods in nuclear engineering
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.2) [13 p.].
- Report number
- INIS-mf--14622
Conference
- Title
- 4. international conference on simulation methods in nuclear engineering.
- Dates
- 2-4 Jun 1993.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 26073956
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CANDU TYPE REACTORS; EXPERIMENTAL DATA; FLOW MODELS; LOSS OF FLOW; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY EXPERIMENTS; SAFETY ANALYSIS; SIMULATION; STEAM GENERATORS; TEST FACILITIES; THERMOSYPHONS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; BOILERS; CONVECTION; COOLING SYSTEMS; DATA; ENERGY TRANSFER; FLUID FLOW; HEAT TRANSFER; HEAVY WATER MODERATED REACTORS; INFORMATION; MATHEMATICAL MODELS; NUMERICAL DATA; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS