U-Tube SG Two-Loop Test Fac/SRI (SET facility)
CCVM Key:
11.30
Country:
United States of AmericaOrganization:
SRI - Standford Research Institute
Operating years:
- 1984
Reference reactor:
Availability:
Objectives:
Main characteristics
Volumetric scale:3200
Number of simulated fuel rods:4
Experimental conditions
Pressure min:0.069 MPa
Pressure max:0.752 MPa
Power min:15 kW
Power max:41 kW
Facility geometry
Keywords General:
- Full Scale (Steam Generator)
- Non Nuclear Core
- Reduced Scale
Keywords Core:
- Downcomer
- Rod Simulator
Keywords Steam Separator:
- Steam Generator (simulator)
Keywords Others:
- Pressurizer (PZR)
References
-
A. L. Kiang, Two-Phase Natural Circulation Experiments in a Test Facility Modeled After Three Mile Island Unit-2, EPRI-NP-2069, 1981
http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/13/664/13664709.pdf?r=1
-
A. L. Kiang, P. A. Jeuck, and J. C. Eid, Decay Heat Removal Experiments in a UTSG Two-loop Test Facility, EPRI-NP-2621, 1982
-
R. L. Kiang, P. A. Jeuck, and J. C. Eid, Decay Heat Removal Experiments in a U-Tube Steam Generator One-loop Test Facility, EPRI-NP-3472, 1984
Phenomena
| Relevance | Phenomenon |
|---|---|
| Heat Transfer : Core | |
| Heat Transfer : SG | |
| Noncondensable gas effects |