Number of loops:4
Number of simulated fuel rods:2048
Pressure min:0.6 MPa
Pressure max:0.6 MPa
Power min:10000 kW
Power max:10000 kW
Keywords General:
Keywords Core:
Keywords Steam Separator:
Data Reports on large scale reflood tests for each CCTF-Experiment.
H. Akimoto and Y. Murao: "Evaluation Report on CCTF Core-I Reflood Tests C1-2 (Run 11) and C1-11 (Run 20) - Effect of the Installment of the Baffle Plates in the Control Rod Guide Tubes and the Spool Piece in the Primary loops". JAERl-M 83-094, 1983
http://jolissrch-inter.tokai-sc.jaea.go.jp/search/servlet/search?3019996
Y. Murao, K. Fujiki and H. Akimoto: "Evaluation Report on CCTF Core-I Reflood Test C-19 (Run 38) - Experimental Assessment of the Evaluation Model for the Safety Analysis on the Reflood Phase of a PWR-LOCA". JAERl-M 83-029, 1983
Y. Murao, T. lguahi: "Evaluation Report on CCTF Core-I Reflood Tests C1-17 (Run 36) and C1-20 (Run 39) -Thermal Multidimensional Effects on Core Thermo-hydrodynamics". JAERl-M 83-028 , 1983
http://jolissrch-inter.tokai-sc.jaea.go.jp/search/servlet/search?3019930&language=1
T. Okubo, T. Iguchi, Evaluation report on CCTF core-II reflood test C2-4 (Run 62), JAERI-M 85-026, 1985
http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/17/073/17073762.pdf
Proc. 2nd Int. Topical Mtg. Nucl. Power Plant Thermohydraulics and Operations 2B-2 (1986) and dito 2B-3 (1986)
Relevance | Phenomenon |
---|---|
Counter Current Flow Limitation (CCFL) | |
ECC Bypass | |
Global Multidimensional Fluid Temperature, Void and Flow Distribution | |
Phase separation | |
Quench Phenomena |