Contribution of IAEA coordinated research projects to light water reactors advanced technology fuel testing and simulation
The Fukushima-Daiichi accident in 2011 highlighted the pressing need for enhanced design and safety analysis of nuclear fuels, especially under accident conditions in nuclear power plants (NPPs). To address this need, the international nuclear fuel community has developed several concepts of Accident Tolerant and Advanced Technology Fuels (ATFs) for light water reactors. The International Atomic Energy Agency (IAEA), at the request of its Member States, has initiated a series of three Coordinated Research Projects (CRPs) to aid in the development and testing of these ATFs. Further, these projects, known as FUMAC, ACTOF, and ATF-TS, focus on the experimentation and simulation of ATFs under various accident conditions, including design basis accidents and design extension conditions. This paper provides a comprehensive overview of the main activities, as well as the achieved or anticipated results of these three CRPs. The insights and advancements gained from these projects will enable IAEA Member States to further refine nuclear fission technology, thereby contributing to efforts aimed at mitigating climate change.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE
- Grant/Contract Number:
- AC07-05ID14517
- OSTI ID:
- 2452747
- Report Number(s):
- INL/JOU--24-77537-Rev000
- Journal Information:
- Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 418; ISSN 0029-5493
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
A model to predict the failure of zircaloy-4 fuel sheathing during postulated loca conditions
|
journal | February 1984 |
Accident tolerant fuels for LWRs: A perspective
|
journal | May 2014 |
From FUMAC and ACTOF to ATF-TS: Contribution of IAEA CRPs to Advanced Technology Fuel Testing, Modelling and Simulation
|
conference | January 2022 |
Burst Criterion of Zircaloy Fuel Claddings in a Loss-of-Coolant Accident
|
book | January 1982 |
| MATPRO-Version 11: a handbook of materials properties for use in the analysis of light water reactor fuel rod behavior | report | February 1979 |
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