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http://dx.doi.org/10.20466/KPVP.202.18.2.037

Influence Analysis on the Number of Ruptured SG u-tubes During mSGTR in CANDU-6 Plants  

Seon Oh Yu (Korea Institute of Nuclear Safety, Univ. of Science and Technology)
Kyung Won Lee (Korea Institute of Nuclear Safety)
Publication Information
Transactions of the Korean Society of Pressure Vessels and Piping / v.18, no.2, 2022 , pp. 37-42 More about this Journal
Abstract
An influence analysis on multiple steam generator tube rupture (mSGTR) followed by an unmitigated station blackout is performed to compare the plant responses according to the number of ruptured u-tubes under the assumption of a total of 10 ruptured u-tubes. In all calculation cases, the transient behaviour of major thermal-hydraulic parameters, such as the discharge flow rate through the ruptured u-tubes, reactor header pressure, and void fraction in the fuel channels is found to be overall similar to that of the base case having a single SG with 10 u-tubes ruptured. Additionally, as the conditions of low-flow coolant with high void fraction in the broken loop continued, causing the degradation of decay heat removal, the peak cladding temperature (PCT) would be expected to exceed the limit criteria for ensuring nuclear fuel integrity. However, despite the same total number of ruptured u-tubes, because of the different connection configuration between the SG and pressurizer, a difference is foud in time between the pressurizer low-level signal and reactor header low-pressure signal, affecting the time to trip the reactor and to reach the PCT limit. The present study is expected to provide the technical basis for the accident management strategy for mSGTR transient conditions of CANDU-6 plants.
Keywords
CANDU-6; SGTR; Multiple events; Fuel channel integrity; MARS-KS code;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
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