| No. |
Title |
Document |
|
|
|
|
Module 1: Introduction to the Code of Conduct |
| L.1.1 |
History, Rationale and Process for Development |
 |
| L.1.2 |
Scope and Contents of the Code |
 |
| L.1.3 |
The Preamble |
 |
| L.1.4 |
Definitions |
 |
|
Module 2: Application of the Guidance (Article III) | |
| L.2.1 |
IAEA Safety Standards |
 |
| L.2.2 |
Graded Approach to Application of Code |
 |
| L.2.3a |
Safety Culture |
 |
| L.2.3b |
Safety Culture |
 |
|
Module 3: The Role of the State in Research Reactor Safety (Article V) | |
| L.3.1a |
Legal and Governmental Infrastructure for Research Reactors: IAEA Safety Standards |
 |
| L.3.1b |
Legal and Governmental Infrastructure for Research Reactors: Regulatory Body Establishment and Authority |
 |
| L.3.1c |
Legal and Governmental Infrastructure for Research Reactors: Financial and Human Resources for the Regulatory Body and the Operating Organization & International Cooperation |
 |
| L.3.1d |
Public Involvement in the Safety of Research Reactors |
 |
| L.3.1e |
Legal and Governmental Infrastructure for Research Reactors: Periodic Review of Safety |
 |
| L.3.1f |
Legal and Governmental Infrastructure for Research Reactors: Cross-Border Notification |
 |
|
Module 4: Role of the Regulatory Body in Research Reactor Safety (Article VI) | |
| L.4.1 |
Desirable Attributes of the Regulatory Process |
 |
| L.4.2a |
Research Reactor Inspection and Enforcement: U.S. Practices |
 |
| L.4.2b |
Selected Topics on Regulatory Oversight of Research reactors - U.S. Practices |
 |
| L.4.2c |
Standard Format & Content for the Safety Analysis Report - U.S. Practices |
 |
| L.4.2d |
Standard Review Plan for the Safety Analysis Report - U.S. Practices |
 |
| L.4.2e |
Interaction of U.S. Social, Technological and Nuclear Regulatory History |
 |
| L.4.2f |
Canadian Nuclear Regulatory System |
 |
| L.4.2g |
IAEA Code of Conduct on the Safety of Research Reactors |
 |
|
Module 5: Role of the Operating Organization in Research Reactor Safety (Article VII) | |
| L.5.1 and L.5.2 |
Operating Organization (Paragraph 21) and General Recommendations (Article VIIA) |
 |
| L.5.3a |
Safety of Research Reactors (Article VIIB) |
 |
| L.5.3b |
Extended Shutdown (Article VIIC) |
 |
| L.5.3c |
Decommissioning (Article VIID) |
 |
| L.5.4 |
Operations at a Large Research Reactor - University of Missouri Research Reactor |
 |
|
Module 6: Role of the IAEA (Article VIII) | |
| L.6.1a |
IAEA Assistance in Applying the Code of Conduct on the Safety of Research Reactors |
 |
| L.6.1b |
The International Nuclear Event Scale |
 |