LTSF Blowdown Quench/INEL (SET facility)
CCVM Key:
11.56
Country:
United States of AmericaOrganization:
INEL - Idaho National Engineering Laboratory (INEL)
Operating years:
1979 - 1983
Reference reactor:
Availability:
Available
Objectives:
Main characteristics
Number of simulated fuel rods:1
Experimental conditions
Pressure min:7 MPa
Pressure max:7 MPa
Facility geometry
Keywords General:
- Non Nuclear Core
Keywords Core:
- Reactor Vessel
- Rod Simulator
Keywords Others:
- Valve
- Pipe
References
-
N. Aksan: "Evaluation of Analytical Capability to predict cladding Quench" EGG-LOFT-5555, August 1982.
-
Gottula, R.C., Good, J.A., Effect of cladding surface thermocouples on the quench behavior of an electrical heater rod, 1980
https://inis.iaea.org/search/searchsinglerecord.aspx?recordsFor=SingleRecord&RN=11552917
-
R. C. Gottula, Effects of cladding surface thermocouples and electrical heater rod design on quench behavior, NUREG/CA-2691, 1984.
https://inis.iaea.org/search/searchsinglerecord.aspx?recordsFor=SingleRecord&RN=15068017
Phenomena
| Relevance | Phenomenon |
|---|---|
| Heat Transfer : Core | |
| Heat Transfer : SG | |
| Quench Phenomena |