Published 1989 | Version v1
Report Restricted

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

Restricted

The record is publicly accessible, but files are restricted to users with access.

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).

Optional Information

Contract/Grant/Project number
Contract AC07-76ID01570
Secondary number(s)
CONF-891103--75.