MAAP [Modular Accident Analysis Program] steam generator modeling and benchmarking with Westinghouse MB-2 tests
- 1. Fauske and Associates, Inc., Burr Ridge, IL (USA)
Description
A generalized theoretical model has been developed and numerically implemented to predict the thermal hydraulic response of a U-tube steam generator during various transients such as steam line break, steam generator tube rupture, loss of feed water, and primary side transients. A two region model is used with a simple and fast running code to calculate essential state variables. It can simulate all the transients from normal to the extreme conditions such as when the secondary side contains superheated steam with non-condensable gases and no water. Comparisons are made to the data of the Westinghouse Model Boiler No. 2 (MB-2) test1 for five types of transient: (1) 100% steam line break from hot standby condition, (2) 50% steam line break from hot standby condition. (3) 8% steam line break with steam generator tube rupture, (4) loss of feedwater from 100% power without reactor scram, and (5) loss of feed water from 100% power with reactor scram. Good agreement is observed between the model predictions and the test data. 9 refs., 16 figs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 as DE90012955; OSTI; INIS.
Files
Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- EGG-M--89161
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21094954
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; M CODES; PWR TYPE REACTORS; REACTOR SAFETY; RUPTURES; STEAM GENERATORS; THERMODYNAMIC MODEL; TRANSIENTS; TUBES; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; MATHEMATICAL MODELS; PARTICLE MODELS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; STATISTICAL MODELS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Secondary number(s)
- CONF-891103--75.