Reverse primary-side flow in steam generators during natural circulation cooling
Description
A TRAC model of the Large Scale Test Facility with a 3-tube steam-generator model was used to analyze natural-circulation test ST-NC-02. For the steady state at 100% primary mass inventory, TRAC was in excellent agreement with the natural-circulation flow rate, the temperature distribution in the steam-generator tubes, and the temperature drop from the hot leg to the steam-generator inlet plenum. TRAC also predicted reverse flow in the long tubes. At reduced primary mass inventories, TRAC predicted the three natural-circulation flow regimes: single phase, two phase, and reflux condensation. TRAC did not predict the cyclic fill-and-dump phenomenon seen briefly in the test. TRAC overpredicted the two-phase natural-circulation flow rate. Since the core is well cooled at this time, the result is conservative. An important result of the analysis is that TRAC was able to predict the core dryout and heatup at approximately the same primary mass inventory as in the test. 4 refs., 8 figs., 2 tabs
Availability note (English)
Available from NTIS, PC A02; 3 as DE87011768.
Files
Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- LA-UR--87-2074
Conference
- Title
- Symposium on technology of glass, ceramic, or glass-ceramic to metal sealing.
- Dates
- 13-18 Dec 1987.
- Place
- Boston, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19046326
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; EVALUATION; HYDRAULICS; LOSS OF COOLANT; MULTIPHASE FLOW; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; PUMPS; PWR TYPE REACTORS; SCALE MODELS; STEAM GENERATORS; T CODES; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID FLOW; HEAT TRANSFER; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; STRUCTURAL MODELS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Paper copy only, copy does not permit microfiche production.
- Secondary number(s)
- CONF-871207--7.