Estimation of the effect of distorted wall condensation of ROSA/AP600 performance
Conference
·
OSTI ID:100675
- Idaho National Engineering Lab., Idaho Falls, ID (United States). Dept. of Engineering Research and Applications
The Large Scale Test Facility of the Japan Atomic Energy Research Institute was selected by the U.S. Nuclear Regulatory Commission to, after suitable modifications, conduct confirmatory testing of the Westinghouse AP600 design. Like all scaled facilities, LSTF has numerous potential sources of scaling distortions. Because of its Full-Height Full-Pressure and power-to-volume scaling design philosophy, vertical surfaces in a modified LSTF are larger than ideal. Such is the case of the Core Makeup Tanks, which in the AP600 design have the double function of providing full pressure coolant to the core. While simultaneously controlling the operation of the Automatic Depressurization System valves that accelerate the depressurization of the primary system. As the CMT drains, steam enters it from the top; the CMT`s liquid level is detected and it triggers the opening of the ADS valves. CMTs, ADS, and their associated logic have been incorporated into the modified LSTF to capture this aspect of AP600 performance. The question that motivated this effort is whether the excessive wall area, available to the steam entering the top of the CMT, can cause excess condensation and significantly distort system performance. A series of sensitivity calculations and engineering analysis were conducted to evaluate this effect. The results indicate that although an effect can be expected, its significance dies out as the transient progresses.
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 100675
- Report Number(s):
- CONF-941142--; ISBN 0-7918-1433-5
- Country of Publication:
- United States
- Language:
- English
Similar Records
Non-condensable gas effects in ROSA/AP600 small-break LOCA experiments
Analysis of wall heat capacity effects on core makup tank drain-down behavior in ROSA/AP600 experiments
ROSA-AP600 experiment simulating a steam generator tube rupture transient
Book
·
Sat Jun 01 00:00:00 EDT 1996
·
OSTI ID:234279
Analysis of wall heat capacity effects on core makup tank drain-down behavior in ROSA/AP600 experiments
Conference
·
Sun Nov 30 23:00:00 EST 1997
·
OSTI ID:549088
ROSA-AP600 experiment simulating a steam generator tube rupture transient
Conference
·
Sun Nov 30 23:00:00 EST 1997
·
OSTI ID:552162