NSUF 17-CINR-12976: Study of the Irradiation Behavior of Fast Reactor Mixed Oxide Annular Fuel with Modern Microstructural Characterization to Support Science Based Model Validation
The objective of this work is to grow the available database of post irradiation data available for annular mixed-oxide (MOX) fuel irradiated in fast spectrum reactors. The key samples for this work are pins from the FO-2 irradiation that was conducted at the Fast Flux Test Facility. These pins are currently located at the Idaho National Laboratory (INL) Hot Fuel Examination Facility (HFEF) hot-cell. The data collected in this project would be used to validate models currently being developed at the Japanese Atomic Energy Agency (JAEA) for fuel performance models that seek to simulate MOX fuel behavior and will be implemented in BISON. Currently the available data for annular MOX fuel performance is limited in comparison to the solid MOX fuel data set. Annular MOX fuel is necessary for high burnup (20% fissions per heavy metal atoms (FIMA)) fuel applications and any developed fuel performance code needs to be able to simulate fuel accurately to these burnups and accurately at lower burnups as well. Pins from the FO-2 irradiations are a key examples of annular MOX irradiated to an intermediate burnup of approximately 6 to 7% FIMA. Very little post-irradiation examination (PIE) has been performed on FO-2 [1, 2] currently and comprehensive PIE of annular fuel pins from FO-2 is needed to provide data for fuel performance codes.This project will directly contribute to the understanding of fast reactror MOX fuel by providing an important data set for the development of future fuel performance models. This project will also create an enduring impact by providing a wide variety of samples at several different local burnup (fission density) and temperature conditions to the NSUF sample library. At the conclusion of this project the prepared microscopy samples will enter the NSUF sample library where they will be available for future measurements that can support additional BISON model development, future MARMOT model development and be available for new techniques as they are developed for PIE. The collaboration proposed in this project between the US Department of Energy (DOE) and JAEA is already facilitated by the current US-Japan Civil Nuclear Working Group Advanced Fuels collaboration. This project would be a high profile portion of this already successful collaboration.
מידע נוסף
| שדה | ערך |
|---|---|
| Awarded Institution | Oak Ridge National Laboratory |
| CINR Number | 17-12976 |
| Embargo End Date | 2032-01-16 |
| NSUF Call | FY 2017 CINR |
| PI | Jason Harp |
| Project Member | Dr. Jason Harp, Group Leader - Oak Ridge National Laboratory (https://orcid.org/0000-0002-5345-8440) |
| Project Type | CINR |
| Publication | Post-irradiation Examinations of Annular Mixed Oxide Fuels Fabiola Cappia, Jason Harp, Kenneth McClellan Global 2019 2019-09-22 - 2019-09-26 |
| Publication | Current Status of Postirradiation Examination of the AFC Metallic Fuel Jason Harp, Luca Capriotti, Fabiola Cappia, Steven Hayes ANS Annual Meeting 2018 2018-06-18 - 2018-06-22 |
| Publication | Electron microscopy characterization of the fuel-cladding interaction in medium burnup annular fast reactor MOX Fabiola Cappia Journal of Nuclear Materials None 2021-04-16 https://www.sciencedirect.com/science/article/pii/S002231152100146X |
| Publication | Post-irradiation examinations of annular mixed oxide fuels with average burnup 4 and 5% FIMA Fabiola Cappia, Kenneth McClellan, Jason Harp Journal of Nuclear Materials 533 2020-03-13 https://doi.org/10.1016/j.jnucmat.2020.152076 |
| RTE Number | 3053 |