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| 001 | 891443 | ||
| 005 | 20240711114035.0 | ||
| 024 | 7 | _ | |a 10.1016/j.nme.2017.01.006 |2 doi |
| 024 | 7 | _ | |a 2128/27508 |2 Handle |
| 024 | 7 | _ | |a WOS:000417293300192 |2 WOS |
| 037 | _ | _ | |a FZJ-2021-01525 |
| 082 | _ | _ | |a 624 |
| 100 | 1 | _ | |a Beckers, M. |0 P:(DE-HGF)0 |b 0 |
| 245 | _ | _ | |a Investigations of the first-wall erosion of DEMO with the CELLSOR code |
| 260 | _ | _ | |a Amsterdam [u.a.] |c 2017 |b Elsevier |
| 336 | 7 | _ | |a article |2 DRIVER |
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| 336 | 7 | _ | |a Journal Article |b journal |m journal |0 PUB:(DE-HGF)16 |s 1616756979_22825 |2 PUB:(DE-HGF) |
| 336 | 7 | _ | |a ARTICLE |2 BibTeX |
| 336 | 7 | _ | |a JOURNAL_ARTICLE |2 ORCID |
| 336 | 7 | _ | |a Journal Article |0 0 |2 EndNote |
| 520 | _ | _ | |a Fusion reactor systems codes (SCs) are 0.5d codes used for optimization studies towards the design of a tokamak demonstration power plant (DEMO). These codes usually comprise a description of the core plasma physics, technology aspects and reactor economy, while only a coarse description of plasma-wall interaction (PWI) aspects is included. Therefore, the new systems code extension CELLSOR (Code to Estimate the Lifetime Limited by Sputtering Of a Reactor wall) was developed in order to allow inclusion of PWI effects into reactor optimization studies. CELLSOR is foreseen to be used as a secondary tool for PWI evaluations, taking design point parameters from the European PROCESS systems code as input. CELLSOR consists of an analytical treatment of the plasma in the scrape-off layer (SOL) for fuel ions (D, T), solving the 1.5d continuity equation in fluid approximation to obtain perpendicular flux and ion density in the SOL, and a fast Monte-Carlo description of the neutral particle (D, T) behavior. The Monte Carlo (MC) implementation of the new code extension was successfully benchmarked with results from the EIRENE code. The trajectories of eroded neutral W were computed within CELLSOR ERO, an add-on code used for calculations of prompt re-deposition and self-sputtering. The damage by ions was calculated analytically for fuel (D, T), ash (He), seeding gas (N) and wall material (W), including the acceleration by a sheath in front of the wall, assuming radially constant impurity concentrations. |
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| 700 | 1 | _ | |a Biel, W. |0 P:(DE-Juel1)129967 |b 1 |e Corresponding author |
| 700 | 1 | _ | |a Tokar, M. |0 P:(DE-Juel1)5089 |b 2 |
| 700 | 1 | _ | |a Samm, U. |0 P:(DE-Juel1)130133 |b 3 |
| 773 | _ | _ | |a 10.1016/j.nme.2017.01.006 |g Vol. 12, p. 1163 - 1170 |0 PERI:(DE-600)2808888-8 |p 1163 - 1170 |t Nuclear materials and energy |v 12 |y 2017 |x 2352-1791 |
| 856 | 4 | _ | |u https://juser.fz-juelich.de/record/891443/files/1-s2.0-S235217911630182X-main.pdf |y OpenAccess |
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