ABOUT TRANSAT
TRANSAT (TRANSversal Actions for Tritium) was a four and a half year multidisciplinary project that contributed to improving the knowledge on tritium management in fission and fusion facilities. It aimed to address the challenges related to tritium release mitigation strategies and waste management improvement, and refine knowledge in the fields of radiotoxicity, radiobiology, and dosimetry.
The project aimed to achieve 3 strategic objectives.
Impact
Various stakeholders contributed to the work carried out in TRANSAT and benefitted from project outcomes. The production, storage, transport and other operations related to tritium will need a more specific framework in the long term. This project brought major inputs to the existing technical and legal frameworks and to the development of appropriate rules, procedures, standards, legislation, etc. The outcomes also brought new technical knowledge to the fission and fusion community, and helped public and private stakeholders prepare for an appropriate global management and financial environment in the short, medium and long term horizon.
NEWS & EVENTS
RESOURCES
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Highly ductile amorphous oxide at room temperature and high strain rate, E. Frankberg, F. di Fonzo et al. Access publication
Bioaccumulation, release and genotoxicity of stainless steel particles in marine bivalve molluscs, E. Vernon, A. Jha, D. Slomberg, V. Malard, C. Grisiola, M. Payet, A. Turner. Access publication
Cyto-Genotoxicity of Tritiated Stainless Steel and Cement Particles in Human Lung Cell Models, Y. Lamartiniere, D. Slomberg, M. Payet, V. Tassistro, A. Mentana, G. Baiocco, J. Rose, L. Lebaron-Jacobs, C. Grisolia, V. Malard, et al. Access publication
Tritium measurements by nuclear reaction analysis using ³He beam in the energy range between 0.7 MeV and 5.1 MeV, S. Markelj, M. Payet, E. Bernard, M. Lipoglašek, M. Kelemen, A. Cvetinović, C. Grisolia, P. Pelicon. Access publication
Double pulse laser-induced plasmas on W and Al by ps-LIBS: Focus on the plasma-second pulse interaction, A. Favre, V. Morel, A. Bultel, S. Idlahcen, A. Benyagoub, I. Monnet, A. Sémérok, M. Dinescu, S. Markelj, P. Magaud, C. Grisolia. Access publication
Comparison of two modelling tools for the evaluation of tritium and hydrogen transfers in nuclear reactors or complex systems, T. Gilardi, C. Moreno, C. Grisolia. Access publication
A 3D In Vitro Model of the Human Airway Epithelium Exposed to Tritiated Water: Dosimetric Estimate and Cytotoxic Effects, G. Baiocco, I. George, S. Garcia-Argote, I. Guardamagna, L. Lonati, Y. Lamartinière, T. Orsière, B. Rousseau, A. Ottolenghi, A. Jha, L. Lebaron-Jacobs, C. Grisolia, V. Malard. Access publication
Absorption of a nanosecond laser pulse by a picosecond laser-induced preformed aluminum plasma, A. Favre, V. Morel, A. Bultel, G. Godard, S. Idlahcen & C. Grisolia. Access publication
Advances on GenIV structural and fuel materials and cross-cutting activities between fission and fusion, L. Malerba, P. Agostini, M. Bertolus, F. Delage, A. Gallais-During, C. Grisolia, K. Liger & Pierre-F. Giroux. Access publication
Development of a viable route for lithium-6 supply of DEMO and future
fusion power plants, T. Giegerich, K. Battes, J.C. Schwenzer & C. Day. Access publication
Overview of the TRANSAT (TRANSversal Actions for Tritium) project, Karine Liger, Christian Grisolia, Ion Cristescu, Carlos Moreno, Véronique Malard, Dave Coombs and Sabina Markelj. Access publication
Thermochemical Non-Equilibrium in Thermal Plasmas, Bultel, V. Morel and J. Annaloro. Access publication
Efficient hydrogen and deuterium permeation reduction in Al2O3 coatings with enhanced radiation tolerance and corrosion resistance, D. Iadicicco, S. Bassini, M. Vanazzi, P. Muñoz, A. Moroño, T. Hernandez, I. García-Cortés, F.J. Sánchez, M. Utili, F. García Ferré
Towards ps-LIBS tritium measurements in W/Al materials, Arnaud Bultel, Vincent Morel, Aurélien Favre, Gilles Godard, Abdenacer Benyagoub, Isabelle Monnet, Alexandre Sémérok, Maria Dinescu, Sabina Markelj, Philippe Magaud & Christian Grisolia.
- D1.1 – Report on the assessment of tritium term sources and on the different types of barrier against tritium permeation relevant for fusion and fission reactors
- D1.2 – Report on the Assessment of a Viable Route for the Separation of Lithium Isotope
- D1.3 – Report on review of gas treatment technologies
- D1.4 Report on active barriers that complement the coating technics
- D1.5 – Report on experimental activities demonstrating transfer of technology under operating conditions of fusion fission
- D2.1 – Review of the different techniques to analyse tritium
- D2.2 – Technical document: Data set about ASTRID design and operating conditions to be simulated
- D3.1 – Report on production of steel particles
- D3.2 – Report on production of cement particles and characterization of steel and cement suspensions
- D3.3 – Report on tritiation of cement and steel particles
- D3.4 Report on model equations and comparison with generic models
- D3.5 Report on development of tools to study the environment fate of particles by products
- D3.7 Report on acute and long-term toxicities on in-vitro human models
- D3.9 Report on predicted effectiveness of tritiated products
- D4.1 – Interim report on the state of the art. Completion of design of experimental study
- D4.2 – Final Report
- D4.3 – Interim report concerning the state of the art. Completion of design of experimental study
- D4.5 – Interim Report Containing Research for Disposal Reuse Neutralisation and Partners Tritium Inventory Measurement
- D4.6 – Disposal or recycling plan for tritium ready
- D5.2 – Dissemination and exploitation plan
- D5.3 – Data Management Plan
- D5.4 – First Summer School Proceedings
- D5.5 Second Summer School Proceedings
- D5.6 – Communication Action Plan
- D5.7 – Project website
- D6.1 – Project Quality Plan
- D6.2 – Detailed Work Plan
PARTNERS
18 partners from 8 European countries worked to improved the knowledge on tritium management over the course of 54 months.
