Abstract
GHARR-1 facility is a Miniature Neutron Source Reactor with a rated power of 30 kW. GHARR-1 was commissioned on 8th March, 1995. The facility has been operating using the Micro-Computer Closed Loop System (MCCLS) and Control Console (CC) for 19 years. Age related degradation effects in safety related systems of nuclear reactors are managed to prevent safety margins from eroding below the acceptable limits provided in reactors design. This paper therefore provides an update on managing the safety aspects of ageing of structures, systems, and components (SSC) of GHARR-1. Managing the safety aspects of research reactors ageing requires a proactive, systematic, and integrated ageing management approach for the coordination of all activities relating to control, monitoring, and mitigation of ageing degradation of SSC through the lifecycle of the GHARR-1. This paper outlines the ageing management program and mitigation practices. Strategies for the ageing management include: periodic safety reviews, design features for components and unit replacement, and succession planning. Information sharing with other operating organizations is one of the means considered by GHARR-1 to attain excellence. This paper again concisely reviews and integrates information developed by other aging management studies and other available information related to understanding and managing age-related degradation effects.DOI: http://dx.doi.org/10.5755/j01.erem.74.3.19974
Highlights
Ageing is a conventional technique where the fea- components or techniques and as a result difficulty tures of systems, structures and components (SSCs) in acquiring spare parts
Upon failure to detect the reductions in these margins, GHARR-1 safety could be impaired except if actions are taken to abate it before loss of operational ability occurs
The Safety Practices Publication Data Collection and Record Keeping for the Management of Nuclear Power Plant Ageing provides information on data requirements and a system for data collection and record keeping for the Ghana Miniature Neutron Source Reactor (MNSR) (Akaho, Anim-Sampong and Dodoo-Amoo, 1995). This project integrates information on the evaluation and management of safety aspects of reactor ageing generated by Member States into a common knowledge base, and derives guidance and assists Member States in the application of this guidance (International Atomic Energy Agency, 1990, 1991, 1992, 1992b, 1999; Kang and Moore, 2013)
Summary
Ageing is a conventional technique where the fea- components or techniques and as a result difficulty tures of systems, structures and components (SSCs) in acquiring spare parts. Introduction of new compoprogressively alter with application or time The physical ageing of GHARR-1 will culminate in deterioration of materials put through general conditions of service. These comprise usual states of operation based on which SSCs are necessitated to function and the anticipated operational occurrences based on which SSCs are requisite to continuing to properly operate. Upon failure to detect the reductions in these margins, GHARR-1 safety could be impaired except if actions are taken to abate it before loss of operational ability occurs. During the life of GHARR-1, advanced technologies have come up leading to the introduction of new
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