IPR-R1 Triga Reactor aging management approach

Abstract

A global nuclear safety regime is in place and is being continuously improved. In this context, the aging management of research reactors is one of the requirements for licensing by the regulatory body. The IPR-R1 Triga reactor, located at the for Nuclear Technology Development Center (CDTN), is a nuclear reactor used primarily to research support. It has been in operation for over 60 years and its activities are expected to continue. Thus, the aging management of components, structures and systems is one of the safety factors included in the Periodic Safety Report and encompasses several programs and activities, following the Specific Safety Guide SSG-10 (Aging Management for Research Reactors) of the International Atomic Energy Agency (IAEA). These programs are broad and transversal, serving as input for critical analysis of the Aging Management Plan (AMP), aimed at its continuous improvement. This paper aims to systematically present information related to the AMP of the CDTN IPR-R1 Triga reactor, such as visual inspection, reactor pool water quality control, maintenance, obsolescence control, investigation of operational parameters and all necessary controls to ensure that the safety margins required in the reactor design are maintained throughout its useful life.

Keywords

• Aging Management
• Triga
• Research reactor