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research-article

Experimental Demonstration of safety of AHWR during Stagnation Channel Break condition in an Integral Test Loop

[+] Author and Article Information
Mukesh Kumar Dhiman

Reactor Engineering Division, Reactor Design and Development Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India
mukeshd@barc.gov.in

Arun Nayak

Reactor Engineering Division, Reactor Design and Development Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India
arunths@barc.gov.in

Sumit Vishnu Prasad

Reactor Engineering Division, Reactor Design and Development Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India
svprasad@barc.gov.in

Purnendra Verma

Reactor Engineering Division, Reactor Design and Development Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India
pkverma@barc.gov.in

Raj Kumar Singh

Reactor Engineering Division, Reactor Design and Development Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India
rajks@barc.gov.in

Vikas Jain

Reactor Engineering Division, Reactor Design and Development Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India
jainv@barc.gov.in

Dinesh Kumar Chandraker

Reactor Engineering Division, Reactor Design and Development Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India
dineshkc@barc.gov.in

1Corresponding author.

ASME doi:10.1115/1.4038899 History: Received May 16, 2017; Revised December 06, 2017

Abstract

Detection of LOCA and generation of reactor trip signal for shutting down the reactor is very important for safety of the nuclear reactor. LBLOCA being the design basis accident in all reactors has attracted attention of the reactor designers. However, studies reveal that SBLOCA is sometimes much severe as it is difficult to detect SBLOCA with conventional methods and generate reactor trip signals for safety of the reactor. SBLOCA in channel type reactor is essential to consider as it may create stagnation channel conditions in the reactor coolant channel, which may lead to fuel failure, if the reactor is not tripped. AHWR is a channel type BWR is prone to stagnation channel break conditions in case of SBLOCA in feeder pipes. For initiating the trip signals and safe shut down of the reactor in such cases, a novel system comprises of acoustic based sensors is incorporated in the reactor design. The system detects the peculiar sound of the steam leaked from the main heat transport system and generates reactor trip signal. The experimental demonstration of such new system is essential before its introduction in the reactor. The experimental demonstration of the stagnation channel break, its detection by acoustic based sensors system and reactor trip followed by generation of reactor trip signal was performed and presented in the paper. The experiment showed that the trip signal for AHWR can be generated within 5 seconds and trip can be initiated within 7 seconds followed by LOCA.

Copyright (c) 2017 by ASME
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