Kuosheng BWR/6 Containment Pressure and Temperature Responses After Recirculation Line Break Using GOTHIC Code
NURETH-14 - 2011 September 25-30


Presented at:
NURETH-14
2011 September 25-30
Location:
Toronto, Canada
Session Title:
E4-1 NPP Transients and Accidents Analysis

Authors:
Ansheng Lin (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)
Jong-Rong Wang (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)
Yen-Shu Chen (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)
Ruey-Yng Yuann (Institute of Nuclear Energy Research Atomic Energy Council, R.O.C.)
Chunkuan Shih (National Tsing Hua University)
  

Abstract

In this study, we presented the calculated results of the containment P/T (pressure and temperature) response after the recirculation line break (RCLB) accident of a GE-designed twin-unit BWR/6 plant, which can be served as the design basis for the containment system. During the simulation, a power of SPU (stretch power uprate) range was used and a model of the Mark III type containment was built using the GOTHIC (Generation of Thermal-Hydraulic Information for Containments) code. The calculated results, similar to the FSAR (Final Safety Analysis Report) results, indicate the GOTHIC code has the capability to simulate the containment P/T response to the RCLB accident.

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