A preliminary assessment for the Divertor Tokamak Test facility Vacuum Vessel (VV) water chemistry was performed using both experiments and simulations. The requirement to use 8000 ppm B in water enriched with 95% 10B as a neutron shield implies that water has a pH60C=3.6. Materials in contact with the borated water are stainless steel type, 316LN, resistant to general corrosion from borated water. Corrosion, however, is a complex phenomenon affected both by water chemistry and material characteristics. No water chemistry guidelines exist for nuclear fusion cooling circuits so the assessment was based on nuclear fission power plants operational experience. The need to add additives to minimize corrosion was assessed using metal release experiments and simulations with the use of computer codes devoted to the estimation of activated corrosion products (ACPs) production and transport. The release of ions induced by general corrosion was found to be more influenced by water chemistry (more releases were measured in the borated water environment than UPW) than microstructure (base metal vs welds). The possible addition of hydrogen in the DTT VV cooling circuit was also assessed, but without considering water radiolysis at this stage. It was found that at these low temperature (60-80°C) the addition of hydrogen seem not beneficial if the oxygen content can be maintained low.
Water Chemistry In Fusion Cooling Systems: Assessment Of Borated Water For The DTT Vacuum Vessel
Gasparrini C.; Martelli E.; Scatigno G.; Di Pace L.; Dalla Palma M.; Terranova N.; Sonato P.; Rizzieri R.;
Villari R.; Roccella S.
Related products
-
Technical Meeting on Synergies in Technology Development between Nuclear Fission and Fusion for Energy Production, , Vienna and online , 6-10 June 2022 Year: 2022
PILOT HYBRID EXPERIMENT WITH REVERSED FIELD PINCH AS NEUTRON SOURCE AND DOUBLE FISSION TEST BEDS: AN INNOVATIVE STAGE APPROACH TOWARDS A FULL POWER FUSION-FISSION HYBRID REACTOR
Piovan R.; Agostinetti P.; Bustreo C.; Cavazzana R.; Cemmi A.; Ciotti M.; Cherubini N.; Escande D.E.; Gaio E.; Lomonaco G.; Lunardon F.; Maistrello A.; Marrelli L.; Murgo S.; Orsitto F.P.; Osipenko M.; Panza F.; Pompeo N.; Puiatti M.E.; Ricco G.; Ripani M.; Valisa M.; Zollino G.; Zuin M.
-
29th IEEE Symposium on Fusion Engineering (SOFE-2021), , Virtual Conference , 12-16 December 2021 Year: 2021
SPIDER, the negative ion source prototype for ITER: first operations with caesium
Serianni G.; Sartori E.; Agnello R.; Agostini M.; Barbisan M.; Bigi M.; Boldrin M.; Brombin M.; Candeloro V.;
Casagrande R.; Dal Bello S.; Dan M.; Duteil B.P.; Fadone M.; Grando L.; Jain P.; Maistrello A.; Mario I.; Pasqualotto R.; Pavei M.; Pimazzoni A.; Poggi C.; Rizzolo A.; Shepherd A.; Ugoletti M.; Veltri P.; Zaniol B.; Agostinetti P.; Aprile D.; Berton G.; Cavallini C.; Cavazzana R.; Cavenago M.; Chitarin G.; Cristofaro S.; Croci G.; Cruz N.; Dalla Palma M.; Delogu R.; De Muri M.; De Nardi M.; Denizeau S.; Fellin F.; Ferro A.; Gaio E.; Gasparrini C.; Luchetta A.; Lunardon F.; Manduchi G.; Marconato N.; Marcuzzi D.; McCormack O.; Milazzo R.; Muraro A.; Patton T.; Pilan N.; Recchia M.; Rigoni Garola A.; Santoro F.; Segalini B.; Siragusa M.; Spolaore M.; Taliercio C.; Zaccaria P.; Zagorski R.; Zanotto L.; Zaupa M.; Zuin M.; Toigo V. -
28th IEEE Symposium on Fusion Engineering (SOFE 2019), , Jacksonville, Florida, USA , June 2-6, 2019 Year: 2019
Overview of the Divertor Tokamak Test Facility project
Albanese R.; Crisanti F.; Martin P.; Pizzuto A.; DTT Team
-
Workshop on Electric Fields, Turbulence and Self-Organization Magentized Plasmas (EFTSOMP 2019), , Padova, Italy , 15-16 July 2019 Year: 2019
3D filamentary transport and the role of edge sheared radial electric fields in the RFX-mod tokamak
Grenfell G.; Spolaore M.; Abate D.; Carraro L.; Marrelli L.; van Milligen B.; Predebon I.; Spagnolo S.; Veranda M.; Agostini M.; Cavazzana R.; Cordaro L.; De Masi G.; Franz P.; Martines E.; Momo B.; Puiatti M.E.; Scarin P.; Vianello N.; Zaniol B.; Zuin M.; RFX-mod Team
English
Italiano