This course gives an overview of Interim storage of spent fuel and will provide engineers/managers with the necessary background information to understand more complicated information. Interim storage of spent fuel will be required until sufficient capacity in permanent geologic repositories or until more advanced technology options become available. Spent fuel is first stored in pools (ponds) located within the nuclear power plant facilities. Given the limited capacity of these installations, additional storage capacity located at either centralised or reactor site facilities are required. In this seminar, the focus will be on the performance of commercial LWR fuel assembly components, with emphasis on Zircaloy-based alloy cladding, during long-term storage of the spent fuel in a dry, inert environment such as helium. Potential degradation mechanisms of cladding alloys will be examined under normal and offset conditions of storage. Changes in cladding mechanical properties will be reviewed in order to properly assess the impact of interim storage upon subsequent spent-fuel management activities, such as transportation.
This course involves watching webinars. Complementary reading is optional to even deepen your knowledge. When all parts of the course have been marked completed you will automatically be issued a certificate. This certificate you may print or share on social media including LinkedIn. If you need a printed certificate, please don’t hesitate to contact us and we will send it to you via regular mail. You reach us at email@example.com.
The course material, including the online content, can be accessed at times convenient for practicing engineers and managers.
The PowerPoint-presentations are available for download on almost all lectures. You will find them just before the lecture starts. (Some presentations are only partial. We apologize for any inconvenience.)
Please note that these PowerPoint-presentations are the actual file from the seminar that has been recorded. Therefore, there may occur spelling errors and/or less perfect pictures or slides. As the presentations are the expert’s own material we have not edited them before making these lectures available online.
If you have any questions regarding this course, please contact support at firstname.lastname@example.org.
The below listed time for the lectures is the actual running time. More time may be needed to digest the information provided in this course.
- Total time: approx. ¼ weeks for full time studies
- Webinars: 10 h
With this course you also get access to our Interim Dry Storage handbook. This is a great complement to this course, but reading time is not included in the overall time listed for this course.
- Managed Storage: A Global Perspective
- Interim Storage Options – Consequences for Transportation
- Radiological Risks
- Zirconium-based Alloy Technology
- Oxidation and Hydriding
- Potential Cladding Degradation Mechanisms During Dry Storage
- Laboratory vs. Deployment Conditions
- Selected R&D Topics
|Dr. Albert Machiels|| Mr. Peter Rudling |
The information presented in this course has been compiled and analysed by Advanced Nuclear Technology International Europe AB (ANT International®) and its subcontractors. ANT International has exercised due diligence in this work, but does not warrant the accuracy or completeness of the information. ANT International does not assume any responsibility for any consequences as a result of the use of the information for any party, except a warranty for reasonable technical skill, which is limited to the amount paid for this course.