A case study and troubleshooting experience of safety power channel of instrumentation and control system of the BAEC TRIGA Research Reactor

Bangladesh Atomic Energy Commission TRIGA Research Reactor (BTRR) is a MK II type nuclear research reactor with a maximum thermal output power of 3 MW. Nuclear research/test reactors are designed for the development of nuclear science and technology including all necessary safety features. Safety is...

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Bibliographic Details
Published in:	Microsystem technologies : sensors, actuators, systems integration Vol. 28; no. 12; pp. 2785 - 2793
Main Authors:	Shohag, Md. Bodhroddoza, Hossain, Md. Sayed, Hasan, Md. Rakibul, Ahmed, Md. Mobasher, Al Mahmud, Abdullah, Uddin, Mohammad Mezbah, Soner, Md. Abdul Malek, Haque, Ashraful, Khan, Kamrul Alam
Format:	Journal Article
Language:	English
Published:	Berlin/Heidelberg Springer Berlin Heidelberg 01-12-2022
Subjects:	Electronics and Microelectronics Engineering Instrumentation Mechanical Engineering Nanotechnology Technical Paper
Online Access:	Get full text
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Summary:	Bangladesh Atomic Energy Commission TRIGA Research Reactor (BTRR) is a MK II type nuclear research reactor with a maximum thermal output power of 3 MW. Nuclear research/test reactors are designed for the development of nuclear science and technology including all necessary safety features. Safety issues are the prime concern for nuclear reactors to protect the nuclear accidents. BTRR has several passive and engineered safety features against any accidental failure of its control mechanisms leading to the meltdown of the reactor core or any other nuclear incident/accident. The nuclear percent power channel (NPP-1000) is one of the vital parts of the safety systems of the BTRR. Suddenly, the Instrumentation and Control (I&C) system of BTRR is tripped with a system SCRAM message “NPP HV Low”. As a safety system, it is very compulsory to resolve the occurred uncertain issue before going to further reactor operation. To solve that kind of unwanted problem, effective troubleshooting steps were taken very carefully. Circuit analysis showed that a fault transistor was found inside the “HV trip circuit”. By replacing this transistor with a good one, the corresponding relay is now functioning successfully and the “NPP HV low trip” condition as well as the "trip alarm" have been removed from the I&C system. Several types of experiments, research and training are now going on using this Bangladesh Atomic Energy Commission (BAEC) TRIGA Research Reactor facility by ensuring proper safety. Different troubleshooting experiences provide various strategies which are helpful for resolving many upcoming problems and also enrich the problem analyzing ability for further known or unknown tasks".
ISSN:	0946-7076 1432-1858
DOI:	10.1007/s00542-022-05366-w