SCTF, JAERI (SET facility)
CCVM Key:
6.14
Country:
JapanOrganization:
JAERI - Japan Atomic Energy Research Institute
Operating years:
-
Reference reactor:
Availability:
Objectives:
Pictures:
Main characteristics
Number of simulated fuel rods:1894
Experimental conditions
Pressure min:0.6 MPa
Pressure max:0.6 MPa
Power max:10000 kW
Facility geometry
Keywords General:
- Non Nuclear Core
Keywords Core:
- Rod Simulator
References
-
Data Reports on large scale reflood tests for each SCTF-test.
-
H. Adachi, et al.: "Design of Slab Core Test Facility (SCTF) in Large Scale Reflood Test Program, Part I: Core-I". JAERl-M 83-080, 1983
http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/15/059/15059460.pdf
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H. Adachi, et al.: "System Pressure Effects on Reflooding Phenomena Observed in the SCTF Core-I Forced Flooding Tests. (Test S1-01 Run 507)". JAERl-M 83-079, 1983
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Proc. of 15th WRS I Meetg. 1988
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Proc. of 16th WRS I Meetg. 1989
Phenomena
| Relevance | Phenomenon |
|---|---|
| Counter Current Flow Limitation (CCFL) | |
| ECC Bypass | |
| Entrainment and Deentainment | |
| Global Multidimensional Fluid Temperature, Void and Flow Distribution | |
| Phase separation | |
| Quench Phenomena |