Effects of ECCS on the Cold-Leg Fluid Temperature during SGTR Accidents
The LSTF experiment simulating the SGTR accident at
the Mihama Unit-2 reactor is analyzed using the RELAP5/MOD3.3
code. In the accident, and thus in the experiment, the ECC water was
injected not only into the cold legs but into the upper plenum. Overall
transients during the experiment such as pressures and fluid
temperatures are simulated well by the code. The cold-leg fluid
temperatures are shown to decrease if the upper plenum injection
system is connected to the cold leg. It is found that the cold-leg fluid
temperatures also decrease if the upper-plenum injection is not used
and the cold-leg injection alone is actuated.
[1] T. Watanabe and Y. Kukita, “Analysis of Experiment Simulating Mihama
Unit-2 Steam Generator U-tube Rupture Incident by using
RELAP5/MOD2,” Proceedings of 28th National Heat Transfer
Conference and Exhibition, San Diego, California, August 9-12, 1992,
Best Estimate Safety Analysis, pp. 1-7 (1992).
[2] M. Hirano and T. Watanabe, “Analyses of the Mihama-2 SGTR Event
and ROSA-IV Experiment SB-SG-06 to Simulate the Event,”
Proceedings of 5th International Topical Meeting on Reactor Thermal
Hydraulics (NURETH-5), Salt Lake City, UT, September 21-24, 1992,
Vol. I, pp. 165-173 (1992).
[3] T. Watanabe and Y. Kukita, “Effects of ECCS and Pressurizer Spray on
the Experiment Simulating Mihama Unit-2 Steam Generator U-tube
Rupture Incident,” Proceedings of 5th International Topical Meeting on
Reactor Thermal Hydraulics (NURETH-5), Salt Lake City, UT,
September 21-24, 1992, Vol. IV, pp. 1013-1020 (1992).
[4] The ROSA-V Group, “ROSA-V Large Scale Test Facility (LSTF)
System Description for the Third and Fourth Simulated Fuel
Assemblies,” JAERI-Tech 2003-037, Japan Atomic Energy Research
Institute (2003).
[5] Y. Kukita, et al., “OECD/NEA/CSNI International Standard Problem No.
26 ROSA-IV LSTF Cold-Leg Small-Break LOCA Experiment
Comparison Report”, NEA/CSNI/R (91)13, OECD/NEA/CSNI (1992).
[6] Nuclear Safety Analysis Division, “RELAP5/MOD3.3 CODE
MANUAL,” Information Systems Laboratories, Inc. (2003).
[1] T. Watanabe and Y. Kukita, “Analysis of Experiment Simulating Mihama
Unit-2 Steam Generator U-tube Rupture Incident by using
RELAP5/MOD2,” Proceedings of 28th National Heat Transfer
Conference and Exhibition, San Diego, California, August 9-12, 1992,
Best Estimate Safety Analysis, pp. 1-7 (1992).
[2] M. Hirano and T. Watanabe, “Analyses of the Mihama-2 SGTR Event
and ROSA-IV Experiment SB-SG-06 to Simulate the Event,”
Proceedings of 5th International Topical Meeting on Reactor Thermal
Hydraulics (NURETH-5), Salt Lake City, UT, September 21-24, 1992,
Vol. I, pp. 165-173 (1992).
[3] T. Watanabe and Y. Kukita, “Effects of ECCS and Pressurizer Spray on
the Experiment Simulating Mihama Unit-2 Steam Generator U-tube
Rupture Incident,” Proceedings of 5th International Topical Meeting on
Reactor Thermal Hydraulics (NURETH-5), Salt Lake City, UT,
September 21-24, 1992, Vol. IV, pp. 1013-1020 (1992).
[4] The ROSA-V Group, “ROSA-V Large Scale Test Facility (LSTF)
System Description for the Third and Fourth Simulated Fuel
Assemblies,” JAERI-Tech 2003-037, Japan Atomic Energy Research
Institute (2003).
[5] Y. Kukita, et al., “OECD/NEA/CSNI International Standard Problem No.
26 ROSA-IV LSTF Cold-Leg Small-Break LOCA Experiment
Comparison Report”, NEA/CSNI/R (91)13, OECD/NEA/CSNI (1992).
[6] Nuclear Safety Analysis Division, “RELAP5/MOD3.3 CODE
MANUAL,” Information Systems Laboratories, Inc. (2003).
@article{"International Journal of Mechanical, Industrial and Aerospace Sciences:70797", author = "Tadashi Watanabe", title = "Effects of ECCS on the Cold-Leg Fluid Temperature during SGTR Accidents", abstract = "The LSTF experiment simulating the SGTR accident at
the Mihama Unit-2 reactor is analyzed using the RELAP5/MOD3.3
code. In the accident, and thus in the experiment, the ECC water was
injected not only into the cold legs but into the upper plenum. Overall
transients during the experiment such as pressures and fluid
temperatures are simulated well by the code. The cold-leg fluid
temperatures are shown to decrease if the upper plenum injection
system is connected to the cold leg. It is found that the cold-leg fluid
temperatures also decrease if the upper-plenum injection is not used
and the cold-leg injection alone is actuated.", keywords = "SGTR, LSTF, RELAP5, ECCS.", volume = "9", number = "9", pages = "1618-5", }