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research-article

Ex-Vessel loss of coolant accident analysis of ITER divertor cooling system during normal operation using modified RELAP/SCADAPSIM/MOD 4.0

[+] Author and Article Information
Satya Prakash Saraswat

Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur, Kanpur 208016, India
satyasar@iitk.ac.in

Prabhat Munshi

Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur, Kanpur 208016, India
pmunshi@iitk.ac.in

Ashok Khanna

Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur, Kanpur 208016, India
akhanna@iitk.ac.in

Chris Allison

Innovative Systems Software, Idaho Falls, ID 83406, USA
iss@cableone.net

1Corresponding author.

ASME doi:10.1115/1.4037188 History: Received March 27, 2017; Revised June 14, 2017

Abstract

The initial design of ITER incorporated the use of carbon fibre composites in high heat flux regions and tungsten was used for low heat flux regions. The current design includes tungsten for both these regions. The present work includes thermal hydraulic modeling and analysis of Ex-Vessel Loss Of Coolant Accident (LOCA) for the divertor cooling system. The purpose of this study is to show that the new concept of full tungsten divertor is able to with stand in the accident scenarios. The code used in this study is RELAP/SCADAPSIM/MOD 4.0. A parametric study is also carried out with different in-vessel break sizes and ex-vessel break locations. The analysis discusses a number of safety concerns that may result from the accident scenarios. These concerns include vacuum vessel pressurization, divertor temperature profile, passive decay heat removal capability of structure and pressurization of Tokamak cooling water system . The results show, that the pressures and temperatures are kept below design limits prescribed by ITER Organization.

Copyright (c) 2017 by ASME
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