Lawrence Shere Alfred K. Hill Timothy J. Mays Rachel Lawless Rosemary Brown Semali P. Perera
The separation of hydrogen isotopes is a vital step in preparing tritium and deuterium fuels for future fusion energy plants. This represents a fundamental challenge to fusion energy since the separation process must be able to handle high throughputs of hydrogen isotopes with a low tritium inventory, as tritium is highly radioactive and hazardo…
PublishedJ. Northall M. Darby A. Cooper A. Hollingsworth A. Wohlers Y. Zayachuk
Erbium hydrides are suitable materials for the long-term storage of hydrogen and this work details the first reported instance of erbium deuteride synthesis via ion beam implantation. This method offers an alternative loading methodology to conventional gas loading with several advantages and these are discussed within. The work also briefly dis…
PreprintJ. Pittard N. Fox A. Hollingsworth M. Lavrentiev A. Wohlers Y. Zayachuk
Diamond’s intrinsic hardness, excellent thermal conductivity and low atomic number make it a highly promising candidate as a plasma facing material. However, as with the previously used graphite, concerns over tritium retention and resultant chemical etching have so far limited research interest in the use of synthetic diamond. In order to study …
Preprint PurchaseGowri Karajgikar Rachel Lawless Tim Xu James O’Callaghan Barry Butler
An investigation was conducted into minimising effective dose to members of the public in the unlikely event of an accident by optimising design parameters and site locations of future fusion power plants. This is part of our defence in depth approach for tritium safety that also includes significant work on the prevention of accidents. Calculat…
Preprint PublishedM. Glugla B. Butler S. Ciattaglia C. Day D. Demange A. Perevezentsev N. Taylor
The DT fuel cycle is rather different to other nuclear fusion topics: it involves handling of a very precious and radiotoxic gas, i.e. tritium, together with deuterium, processing of gaseous, liquid and solid hydrogen isotopologues, treatment of deuterated and tritiated species, and removal and recovery of deuterium / tritium from water and othe…
PreprintT. Tijssen B. Butler
The tritium inventory of future fusion power plants needs to be monitored in the fuel cycle for several reasons; to comply with limits imposed by environment and safety regulators, adhere to practises required by nuclear regulators and for process control purposes. Fulfilling all these requirements leads to a comprehensive list of locations in the …
Preprint PublishedRebecca Shaw Barry Butler
An initial safety analysis of a preliminary DEMO tritium fuel cycle has been undertaken using functional failure mode and effects analysis (FFMEA) to create accident scenarios for evaluation. A total of ten scenarios were developed and analysed based upon the current technology planned for the tritium fuel cycle. The findings indicate that the pote…
Preprint PublishedChr. Day K. Battes B. Butler S.Davies L. Farina A. Frattolillo R. George T. Giegericha S. Hanke T. Härtl Y. Igitkhanov T. Jackson N. Jayasekera Y. Kathage P.T. Lang R. Lawless X. Luo C. Neugebauer B. Ploeckl A. Santucci J. Schwenzer T. Teichmann T. Tijssen S. Tosti S. Varoutis A. Vazquez Cortes
In the Pre-Concept Design Phase of EU DEMO, the work package TFV (Tritium – Matter Injection – Vacuum) has developed a smart and tritium self-sufficient three-loop fuel cycle architecture. Driven by the need to reduce the tritium inventory in the systems to an absolute minimum, this requires the continual recirculation of gases in loops without…
Preprint PurchaseA. Hollingsworth M.-F. Barthe M.Yu. Lavrentiev P.M. Derlet S.L. Dudarev D.R. Mason Z. Hub P. Desgardin J. Hess S. Davies B. Thomas H. Salter E.F.J. Shelton K. Heinolade K. Mizohatad A. De Backera A. Baron-Wiechec I. Jepuh Y. Zayachuka A. Widdowson E. Meslini A. Morelleci
Self-ion irradiation of pure tungsten with 2 MeV W ions provides a way of simulating microstructures generated by neutron irradiation in tungsten components of a fusion reactor. Electron microscopy has been used to characterize defects formed in tungsten samples by ion irradiation and estimate their density and size distribution. Some of the sample…
Preprint PublishedR. F. Knights J. Benayas K. Sabin S. Ng A. Wohlers T. Tijssen D. Demange S. Willms D. Brennan
The ITER Tokamak Exhaust Processing (TEP) system relies on palladium membrane reactors (PMRs) for tritium recovery. The PMR consists of a palladium/silver membrane permeator filled with a catalyst, that can be used to recover hydrogen species (most importantly tritium) from methane and water impurities present in fusion reactor exhaust emissions…
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