%0 Journal Article %@holdercode {isadg {BR SPINPE} ibi 8JMKD3MGPCW/3DT298S} %@nexthigherunit 8JMKD3MGPCW/3ET2RFS %@archivingpolicy denypublisher denyfinaldraft24 %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid %@resumeid 8JMKD3MGP5W/3C9JHSB %@usergroup administrator %@usergroup marciana %@usergroup sergio %3 analytical erosion.pdf %@secondarytype PRE PI %P 271-275 %4 sid.inpe.br/marciana/2005/03.10.10.32 %X A self-consistent analytical solution for net erosion of a divertor plate which is set perpendicular to magnetic field lines is presented. The primary flux profile of hydrogen and impurities except redepositing particles is externally given as well as the return ratio of sputtered atoms to the plate. In the direction along the divertor trace, all conditions are uniform. The ionization mean free path is assumed constant to simplify equations. The analytical solution is compared with net erosion experiments carried out in compact helical system (CHS) by exposing a graphite target to a neutral beam heated plasma column introduced perpendicularly to the target along the magnetic field lines through a 2 cm slit opened on a graphite limiter. After exposure to 98 discharges, the target surface is analyzed with Rutherford backscattering method. Deposition profiles of Ti and O impurities are very well explained with the analytical predictions. %8 Dec. %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group %@group LAP-INPE-MCT-BR %@issn 0022-3115 %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation Crystalline Materials Science, Nagoya University %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation MIT Plasma Fusion Center %@affiliation Plasma Science Center, Nagoya University %@affiliation National Institute for Fusion Science %@affiliation National Institute for Fusion Science %@affiliation Instituto Nacional de Pesquisas Espaciais, Laboratório Associado de Plasma (INPE.LAP) %@affiliation MIT Plasma Fusion Center %@affiliation National Institute for Fusion Science %D 1992 %A Sagara, A., %A Noda, N., %A Akiyama, R., %A Arimoto, H., %A Idei, H., %A Iguchi, H., %A Kaneko, O., %A Kohmoto, T., %A Kubo, S., %A Matsunami, N., %A Matsuoka, K., %A Morita, S., %A Motojima, O., %A Nishimura, K., %A Okamura, S., %A Rice, J., %A Shojit, T., %A Takahasi, C., %A Takita, Y., %A Ueda, Mário, %A Yamada, H., %A Yamada, I., %@area FISPLASMA %T An Analytical Erosion Model for Divertor Plates and Limiter Experiments in Chs %@visibility shown %@copyholder SID/SCD %@project Tecnologia de plasma: processos a plasma %B Journal of Nuclear Materials %V 196 %@dissemination WEBSCI %K PLASMA, Erosion, Magnetic field, Compact helical system,PLASMA, Erosão, Campos magnéticos, CHS. %@secondarykey INPE-12828-PRE/8118 %2 sid.inpe.br/marciana/2005/03.10.10.32.13