A liquid injection based Second Shutdown System for a typical material testing research reactor. (May 2018)

• Record Type: Journal Article
• Authors: Boustani, Ehsan; Khakshournia, Samad
• Is Part Of: Annals of nuclear energy. Volume 115(2018)
• Page Start: 487
• Page End: 493
• Publication Date: 2018-05
• Subjects: MTR Material Testing Reactor -- SSS Second Shutdown System -- ESF Engineered Safety Feature -- TRR Tehran Research Reactor -- RPS Reactor Protection System -- FSS First Shutdown System -- FOC First Operating Core -- SFE Standard Fuel Element -- CFE Control Fuel Element -- GR Graphite box -- IR Irradiation box -- SRF Safety Reactivity Factor; Tehran Research Reactor -- Nuclear safety -- Safety criteria -- Engineered Safety Feature -- Material Testing Reactor -- Second Shutdown System; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2018.01.047
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: Safety necessities for increasing safety for research reactors are put forward. Comprehensive survey on requirements of one second shutdown system is performed. Designing of one second shutdown system as an engineered safety feature is proposed. Two conceivable Second Shutdown System (SSS) layout are presented. The effect of implementing one SSS on the TRR core parameters is assessed. Abstract: Many research reactors are used all over the world. There is a higher probability of accidents in nuclear research reactors compared their wide applications in a broad spectrum of sciences and industries. Material Testing Reactor (MTR) type is one large species of nuclear research reactors. Safety criteria are of main concern issues in the entire nuclear research reactor lifetime to satisfy the defense in depth criteria. In this paper, the main focus is on Second Shutdown System (SSS) as an Engineered Safety Feature (ESF) considered to enhance safety which will transfer the reactor to a subcritical state at actuation of any command circuits when a specific parameters exceeds some pre-established set points. Tehran Research Reactor (TRR) is selected as an MTR case study and one SSS is designed and studied in detail using MCNPX 2.6.0 code with regard to its requirements. It turns out that this SSS improves the overall reactor safety, and has not considerable penalties on different capabilities and characteristics of the reactor such as neutronic characteristics, safety criteria, and performance applications.