TBL (IET facility)
JapanMain characteristics
Coolant:Water
Primary system volume:1.6 m3
Primary system pressure (max):7.2 MPa
Core flow area:0.0232 m2
Nb jet pumps:2
Nb recirculation loops:2
Scaling method:P-to-V(Kv)
Time scale:1
Volumetric scale:1/350
Height scale:1
Scaling approaches:
- Non-Nuclear Core
- Equal Number Recirculation Loop
- Full Height
- Reduced Number of Jet Pump
- Full Pressure
- Steam - Liquid Water
- Full Power
- Time Preserved
Core
Number of sim. fuel Rods:126
Diameter:12.5 mm
Pitch:16.2 mm
Heated length:3.7 m
Max power:10 MW
Axial Peaking factor:1.4
Heating method:Indirect
Axial power distribution:Chopped cosine
References
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TBL/311, Two Bundle Loop Facility, Small Break in Recirculation Line
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M Murase, M Naitoh: BWR Loss of Coolant Integral Tests with Two Bundle Loop J. of Nuclear Science and Technology, 22, No.3, March 1985
https://www.tandfonline.com/doi/abs/10.1080/18811248.1985.9735649
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T. IKEDA, A. YAMANOUCHI, M. NAITOH : BWR Recirculation Line Break Simulation Tests at Two Bundle Loop, 1984
https://www.tandfonline.com/doi/abs/10.1080/18811248.1985.9735656
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M Murase, M Naitoh, T Gomyoo: BWR Loss of Coolant Integral Tests: Parallel Channel Effect (TBL run 108), Int.ยท Meeting on thermal Nuclear Reactor Safety, Chicago, August 29 - Sept 2, 1982
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T Ikeda: Main Steam Line Break Simulation Tests at TBL, ERL Research Report No. 1497, Itachi Ltd., January 1984