Project Highlights
Deliverables
- D1.2 Report on scenario calculations – September 2022
- D1.4 Report on Impact of fuel cycle analysis in facilities and transport and economic evaluation – September 2023
- D1.5 Synthesis of the impact of the Pu management in the fuel cycle – September 2024
- D2.9 Methodological standards proposal for safety analysis of high Pu fuels – September 2024
D3.1 State of the art on MOX thermal properties with atomic scale modelling. New calculations and requirements for new measurements – September 2022
D3.3 State of the art on MOX mechanical properties. Requirements on measurements of mechanical properties – September 2022
D3.4 Finite element modelling of fuel rod – September 2022
D3.5 Calculation of melting temperature with CALPHAD based on recent measurements – September 2022
D3.6 Effect of burn up and uncertainties on the melting temperature – September 2024
D3.9 New MOX fuel properties catalogue (20 – 45% Pu range) – September 2024
- D4.1 Comparison of MTR and FR core characteristics and related fuel pin performance – March 2022
- D4.2 Irradiation condition requirements for FR fuel qualification and the applicability of FR and MTR – September 2022
- D4.3 Comparison of MTR and FR fuel irradiation experiments for assessment of the validity of MTR irradiations for FR fuel qualifications – May 2023
- D5.1 Co-ordination of Pu-active and HA dissolution experiments WP5 13 – March 2022
- D5.5 Impact of high Pu content MOx fuels on the first step of reprocessing – September 2024
- D6.1 Secondment of students’ report – September 2024
- D6.2 Database on workshops, seminars and courses in Euratom projects – September 2024
- D6.3 E&T materials: eplatform “Wiki-FUEL”, MOOC – September 2024
- D6.4 Workshops report – October 2023
- D6.5 Communication and Dissemination strategy action plan
- D6.6 Communication toolbox: design flyer, set up website and create social media accounts
- D7.3 Project Quality Plan – December 2020
Publications
- Effects of irradiation on the insolubility of sodium fast reactor (U,Pu)O2 mixed oxide with a very high amount of plutonium
- Analysis of advanced European nuclear fuel cycle scenarios including transmutation and economic estimates
- Presentation of the new European project PuMMA, devoted to Plutonium management in the whole fuel cycle
- First Post Irradiation Examinations on a fast reactor grade MOX fuel (U0.6,Pu0.4)O2 for Pu-burning application, irradiated in the High Flux Reactor
- Development of a Dynamic-Mesh Porosity Transport Model for Multi-Dimensional Fuel Performance Codes
- PuMMA blind benchmark: Performance of high plutonium content MOX fuel under irradiation
- ALFRED-burner: Core design, safety and performance
- Off-centering effects on MOX fuel behavior
- Modelling and assessment of thermophysical properties of Am-bearing fuels for transmutation purposes in fast reactors