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Dirk Mallants

Evaluation of the radiological consequences of tritium present in radioactive components from fusion reactors Task TW4-TSW-001-D1b: Waste and decommissioning strategy: waste disposal criteria. Dirk Mallants. Objectives & Methodology.

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Dirk Mallants

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  1. Evaluation of the radiological consequences of tritium present in radioactive components from fusion reactorsTask TW4-TSW-001-D1b: Waste and decommissioning strategy: waste disposal criteria Dirk Mallants

  2. Objectives & Methodology • Current practice in fusion waste management studies: use of acceptance criteria (WAC) derived from Fission waste • Objective: Evaluate if WAC appropriate for fusion waste • Develop approach for deriving fusion-specific WAC • Based on Safety Assessment Modelling (leaching) • Methodology developed for LILW (fission), applied here for SEAFP-2 plant model (representative for PPCS plant model A) • Disposal concept: multi-barrier surface repository • Inventory: tritium after 100 y cooling (5.61017 Bq), mainly in LiPb (breeder: 5.51017 Bq) (e.g., no compliance with El Cabril WAC) • Release mechanism: diffusion in solids & porous media (concrete engineered barriers)

  3. Results 2D tritium profiles in repository Annual total dose for groundwater pathway

  4. Conclusions • If post-closure institutional control is in place: • Zero release (no radiological impact on groundwater) • Institutional control is required for at least 100 y to monitor tritium release • If post-closure institutional control is ineffective: • Radiological impact << dose limit for public (1 mSv/y) if repository filling is optimized (waste is acceptable) • If filling is not optimized: Radiological impact  dose limit • Other (long-lived) radionuclides need to be included in safety assessment • Need to develop fusion specific acceptance criteria accounting for fusion-specific waste characteristics • Optimization of disposal design and practices to accommodate fusion waste in surface repositories

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