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000830232 1001_ $$0P:(DE-Juel1)5247$$aWiesen, S.$$b0$$eCorresponding author$$ufzj
000830232 245__ $$aControl of particle and power exhaust in pellet fuelled ITER DT scenarios employing integrated models
000830232 260__ $$aVienna$$bIAEA$$c2017
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000830232 520__ $$aThe integrated model JINTRAC is employed to assess the dynamic density evolution of the ITER baseline scenario when fuelled by discrete pellets. The consequences on the core confinement properties, α-particle heating due to fusion and the effect on the ITER divertor operation, taking into account the material limitations on the target heat loads, are discussed within the integrated model. Using the model one can observe that stable but cyclical operational regimes can be achieved for a pellet-fuelled ITER ELMy H-mode scenario with Q  =  10 maintaining partially detached conditions in the divertor. It is shown that the level of divertor detachment is inversely correlated with the core plasma density due to α-particle heating, and thus depends on the density evolution cycle imposed by pellet ablations. The power crossing the separatrix to be dissipated depends on the enhancement of the transport in the pedestal region being linked with the pressure gradient evolution after pellet injection. The fuelling efficacy of the deposited pellet material is strongly dependent on the E  ×  B plasmoid drift. It is concluded that integrated models like JINTRAC, if validated and supported by realistic physics constraints, may help to establish suitable control schemes of particle and power exhaust in burning ITER DT-plasma scenarios.
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000830232 7001_ $$0P:(DE-HGF)0$$aKöchl, F.$$b1
000830232 7001_ $$0P:(DE-HGF)0$$aBelo, P.$$b2
000830232 7001_ $$0P:(DE-Juel1)6121$$aKotov, V.$$b3$$ufzj
000830232 7001_ $$0P:(DE-HGF)0$$aLoarte, A.$$b4
000830232 7001_ $$0P:(DE-HGF)0$$aParail, V.$$b5
000830232 7001_ $$0P:(DE-HGF)0$$aCorrigan, G.$$b6
000830232 7001_ $$0P:(DE-HGF)0$$aGarzotti, L.$$b7
000830232 7001_ $$0P:(DE-HGF)0$$aHarting, D.$$b8
000830232 773__ $$0PERI:(DE-600)2037980-8$$a10.1088/1741-4326/aa6ecc$$gVol. 57, no. 7, p. 076020 -$$n7$$p076020 -$$tNuclear fusion$$v57$$x0029-5515$$y2017
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