EBP-ASIA-288

Regional Workshop on: Application of the code of conduct on the safety of research reactors, 30 April–11 May 2007, Argonne National Laboratory, Illinois, USA

Contributions submitted by external experts have not been edited by the IAEA. The views expressed remain the responsibility of the named authors and do not necessarily reflect those of the government(s) of the designating Member State(s). In particular, neither the IAEA nor any other organization or body sponsoring this meeting can be held responsible for any material reproduced in this document.

No.	Title	Document

	Presentations
1	IAEA Safety Standards for Research Reactors Part I
2	IAEA Safety Standards for Research Reactors Part II
3	History of the Code of Conduct on the Safety of Research Reactors
4	The Code of Conduct on the Safety of Research Reactors
5	Safety Standards and Publications Useful in Applying the Code of Conduct on the Safety of Research Reactors
6	Overview of Nuclear Safety Education and Training Material
7	Legal Aspects and Commitments to the Code of Conduct on the Safety of Research Reactors
8	The Open-ended Meeting on Effective Application of the Code of Conduct on the Safety of Research Reactors
9	Benefits from implementing the Code of Conduct on the Safety of Research Reactors
10	Basic Principles of Nuclear Safety
11	Overwiew of regulation on safety of research reactors in Indonesia
12	Implementation code of conduct on the safety of research reactor in BATAN
13	Code of conduct on the safety of research reactor - Thailand
14	Light show at the Grand Palace / Report on the Safety Supervision for Research Reactors in Thailand
15	Implementation of the Code of Conduct in Japan
16	The role of the RB in the operational safety of Dalat research reactor (Vietnam)
17	The current status of Dalat nuclear research reactor on application of code of conduct (Vietnam)
18	Safety assessment and verification in the regulatory body and the operating organisation (French Research Reactor Case)
19	Overview of deterministic and probabilistic safety analysis methods
20	Safety Assessment of Core Conversion
21	Self-assessment Report for HANARO (Rep. of Korea)
22	Safety Assessment of a New Research Reactor: OPAL
23	Management Systems
24	Management Systems for the Operating Organizations of Research Reactors
25	Introduction to Safety Culture – Basic Concepts and Principles
26	Structure and Development of Safety Culture
27	Safety culture in an operating organization
28	Reduction of Human Errors in Operations – A brief Summary of Recent Developments
29	Guidance for the Recruitment, Training and Qualification and Authorisation of Personnel for Research Reactors
30	Personnel Training in JAEA
31	Introduction to Emergency Response / Emergency Preparedness
32	Requirements for Site Evaluation
33	Overview of Safety Considerations in Extended Shutdown
34	Agency Guidance on Decommissioning of Research Reactors
35	Experience in Decommissioning of Research Reactors