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A case study and troubleshooting experience of safety power channel of instrumentation and control system of the BAEC TRIGA Research Reactor
Microsystem Technologies ( IF 2.1 ) Pub Date : 2022-09-21 , DOI: 10.1007/s00542-022-05366-w
Md. Bodhroddoza Shohag , Md. Sayed Hossain , Md. Rakibul Hasan , Md. Mobasher Ahmed , Abdullah Al Mahmud , Mohammad Mezbah Uddin , Md. Abdul Malek Soner , Ashraful Haque , Kamrul Alam Khan

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".



中文翻译:

BAEC TRIGA研究堆仪控系统安全电源通道案例分析及故障排除经验

孟加拉国原子能委员会 TRIGA 研究堆(BTRR)是一座 MK II 型核研究堆,最大热输出功率为 3 MW。核研究/试验反应堆是为发展核科学和技术而设计的,包括所有必要的安全功能。安全问题是核反应堆保护核事故的首要问题。BTRR 具有多项被动和工程安全功能,可防止其控制机制的任何意外故障导致反应堆堆芯熔化或任何其他核事故/事故。核百分比功率通道 (NPP-1000) 是 BTRR 安全系统的重要组成部分之一。突然,BTRR 的仪表和控制 (I&C) 系统因系统 SCRAM 消息“NPP HV Low”而跳闸。作为安全系统,在继续反应堆运行之前解决已发生的不确定问题是非常有必要的。为了解决这种不需要的问题,我们非常谨慎地采取了有效的故障排除步骤。电路分析表明,在“高压跳闸电路”内部发现了一个故障晶体管。通过用一个好的晶体管替换这个晶体管,相应的继电器现在可以正常工作,并且“NPP HV 低跳闸”条件以及“跳闸警报”已从 I&C 系统中移除。通过确保适当的安全性,目前正在使用这个孟加拉国原子能委员会 (BAEC) TRIGA 研究堆设施进行多种类型的实验、研究和培训。

更新日期:2022-09-21
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