Commenced in January 2007
Frequency: Monthly
Edition: International
Paper Count: 30077
Effects of ECCS on the Cold-Leg Fluid Temperature during SGTR Accidents

Authors: Tadashi Watanabe

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.

Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1108663

Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 1444

References:


[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).