O. Vallhagen I. Pusztai M. Hoppe S. L. Newton T. Fülöp
An effective disruption mitigation system in a tokamak reactor should limit the exposure of the wall to localized heat losses and to the impact of high current runaway electron beams, and avoid excessive forces on the structure. We evaluate with respect to these aspects a two-stage deuterium-neon shattered pellet injection in an ITER-like plasma, u…
Preprint PublishedV.H. Hall-Chen J. Damba F.I. Parra Q.T. Pratt C.A. Michael S. Peng T.L. Rhodes N.A. Crocker J.C. Hillesheim R. Hong S. Ni W.A. Peebles C.E. Png J. Ruiz Ruiz
We use the beam model of Doppler backscattering (DBS), which was previously derived from beam tracing and the reciprocity theorem, to shed light on mismatch attenuation. This attenuation of the backscattered signal occurs when the wavevector of the probe beam’s electric field is not in the plane perpendicular to the magnetic field. Correcting …
PublishedO. El Atwani H.T. Vo M. Tunes C. Lee A. Alvarado N. Krienke J. Poplawsky A.A. Kohnert J. Gigax W.-Y. Chen M. Li Y. Wang J.S. Wróbel Duc Nguyen-Manh J.K.S. Baldwin U. Tukac E. Aydogan S. Fensin E. Martinez
In the quest of new materials that can withstand severe irradiation and mechanical extremes for advanced applications (e.g. fission reactors, fusion devices, space applications, etc), design, prediction and control of advanced materials beyond current material designs become a paramount goal. Here, though a combined experimental and simula…
PreprintD. Power S. Mijin F. Militello R. Kingham
Tokamak edge (scrape-off layer) plasmas can exhibit non-local transport in the direction parallel to the magnetic field due to steep temperature gradients.This effect along with its consequences has been explored at equilibrium fora range of conditions, from sheath-limited to detached, using the 1D kinetic electron code SOL-KiT, where the electrons…
PreprintA. Shepherd B. Pouradier Duteil T. Patton A. Rigoni G. Serianni E. Sartori. A. Pimazzoni
SPIDER (Source for the Production of Ions of Deuterium Extracted from a Radio frequency plasma) is the full scale prototype for the ITER Heating Neutral Beam (HNB) source. Driven by four driver coil pairs powered by oscillators the SPIDER source plasma exhibits fluctuations in a range of frequencies that have been observed by Langmuir probes and So…
PreprintRebecca 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 PublishedJ. Lovell M. L. Reinke A. R. Field B. A. Lomanowski the MAST Upgrade team
The MAST Upgrade tokamak has a suite of foil bolometers to measure the total radiated power from the plasma. Arrays of bolometers provide coverage of the main chamber and lower divertor radiation. Data is digitised and processe…
Preprint PurchaseAndrew M. Alvarado Hi Vo Tin Jan S. Wr´obel Damian Sobieraj Duc Nguyen-Manh Saryu Jindal Fensin Enrique Martinez Osman El-Atwani
We present a Density Functional Theory-based cluster expansion model to predict the configurational energy of a multicomponent W-Ta-Cr-V-Hf quinary alloy. Coupled with Monte Carlo simulations we show that the model reproduces experimental observations. We analyze the thermodynamic properties of the W.31Ta.34Cr.05V.27Hf.03 system and observe two ph…
PreprintLei Tang Fuqing Jian Yiqiang Wang Saurabh Kabra Biao Cai
Manufacturing austenite stainless steels (ASSs) using additive manufacturing (AM) is of great interest for cryogenic applications. Here, the mechanical and microstructural responses of a 316L ASS built by laser powder-bed-fusion (L-PBF) were revealed by performing in situ neutron diffraction tensile tests at the low-temperature range (from 373 to 1…
PreprintMaria Lorena Richiusa Wayne Arter Mehdi Firdaouss Jonathan Gerardin Francesco Maviglia Zsolt Vizvary
The charged particle heat load assessed for the DEMO Single Module Segment First Wall (FW) during current off-normal plasma scenarios underlines that protection is needed for avoiding/reducing damage to the Breeding Blanket FW due to the deposition of a huge amount of energy in a small timescale. Within the “Key Design Integration Issue 1”, an…
Preprint Published