Fukushima Type Severe Accident Analysis of Laguna Verde Nuclear Power Plant using RELAP5/SCDAPSIM
33rd Annual CNS Conference - 2012 June 10-13


Presented at:
33rd Annual CNS Conference
2012 June 10-13
Location:
Saskatoon, Canada
Session Title:
Special Topics of Interest

Authors:
A. K. Trivedi (Indian Institute of Technology, Kampur)
Ashok Khanna (Indian Institute of Technology, Kampour)
Prabhat Munshi (Indian Institute of Technology, Kampur)
C Allison (Innovative Systems Software)
  

Abstract

Station black out (SBO) transient in the Boiling Water Reactor (BWR) of Laguna Verde Nuclear Power Plant (LVNPP) is analyzed in the current work. LVNPP model includes reactor vessel, recirculation loops and main steam supply system. It is a BWR-5 containing 444 assemblies with rated power 2317 MWt. Each flow channel is modeled as a pipe divided into 14 nodes. Two recirculation loops were modeled using generic RELAP components for recirculation pumps, valves and jet pumps. A single jet pump is modeled as equivalent to 10 Laguna Verde jet pumps in both recirculation loops. Physical and thermodynamic properties of both loops are identical. There are four steam lines and they are considered separately in the model. The LVNPP model is developed for the format of RELAP5/SCDAPSIM code. This code, designed to predict behavior of PWR/BWR systems during normal and accident conditions, is currently under development at Innovative Systems Software (ISS) as part of the international SCDAP Development and Training program (SDTP). It uses RELAP5/SCDAP models developed by US Nuclear Regulatory Commission (USNRC). It is a combination of RELAP5 code thermal-hydraulic calculation, SCDAP code for severe accident related phenomena and COUPLE code for a finite element of vessel lower head. SCDAP fuel rod and control components use 2D models to predict temperature (r,z), deformation, chemical interactions and melting. The SBO transient is modeled as closure of main steam isolation valves (MSIV) with failure of emergency core cooling systems (ECCS). These events lead to loss of cooling in the core, severe damage of the fuel and hydrogen production. This transient has been run for 23000 seconds. The maximum core surface temperature has gone up to 3000 K with total hydrogen accumulation about 430 kg. The maximum debris temperature in the lower plenum is 4233 K.

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