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| Safety analysis of research reactors (SA) |
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About topical group.
Workshop on "Safety Analysis Methodology and Utilization of Computer Code" was held in 2001-2002 and evaluated a successful example of EBP projects.
Need to maintain the knowledge exchange among the participants in the workshop was agreed at the close of the series of workshops in November 2002 in Korea.
Consequently, follow-up activity, to sustain their corporate memory acquired from the workshop, was proposed.
As a follow-up activity, establishment of "thematic group" addressing topics such as Safety Analysis, Quality Assurance, Operational Limits and Conditions, Emergency Planning, Regulatory Activities, and Safety Culture was initiated.
This thematic group on Safety Analysis will provide a forum for the exchange of information and documentation among specialists dealing with safety analysis of research reactors.
It can be used as a means to maintain and improve the knowledge acquired during the workshop.
A framework of this thematic group is featured as follows.
- Membership: The workshop participants only such as lecturers, IAEA technical experts and workshop recipients.
- Operation method: On a voluntary basis, it is led by an elected system operator among the members.
- Contents: WhatsNew / News / Notice/ Q&A / Photo Gallery / Data Room / Schedule / Free board / Hot Issue
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| Safety analysis of research reactors |
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