LHD [1] is a superconducting helical device (heliotron type) capable of studying current-less plasmas. Experiments are usually performed with hydrogen (H) plasma, with the majority of heating provided by 5 H neutral beam injectors (NBIs). The use of deuterium (D) is planned in the future LHD campaigns, together with the upgrade of at least 3 NBIs to D injection. In tokamak devices it is already known that the increase of plasma ion mass leads to better confinement properties [2,3]. The presence of isotope effect in helical machines is under investigation and modelling of D helical plasmas can help in the prediction of the confinement properties for future D LHD experiments, and, generally, for extrapolation to helical fusion reactors. Interpretative analyses of the LHD experiments are currently carried out with TASK3D-a integrated transport code [4], capable of treating hydrogen and multi-ion species plasma [5,6]. Effort has been recently put to start the upgrade of TASK3D-a code to extend the analysis capabilities to D plasmas with D NBIs. The present paper introduces the first modifications of the NBI module of TASK3D-a code. The neutral beam ionization code has been improved to consider the injection of D beams in D plasma with various impurities, and a module which estimates the neutron rate production for D-D reactions has been implemented in the code. Both thermal and beam-plasma reactions are taken into account for neutron rate estimation with a simplified approach. This paper critically discusses the first results and benchmarking of the recently updated NBI module of TASK3D-a code for modelling of LHD future D experiments. [1] O. Motojima et al, Nucl. Fusion 40 (2000) 599 [2] J. G. Cordey et al., Plasma Phys. Control. Fusion 42 (2000) A127-A132 [3] H. Urano et al., Nucl. Fusion 52 (2012) 114021 [4] M. Yokoyama et al., Plasma Fusion Res. 8 (2013) 2403016 [5] A. Sakai et al., Plasma Fusion Res. 9, (2014) 3403124 [6] H. Yamaguchi and S. Murakami, Plasma Fusion Res. 9 (2014) 3403127

Nbi modelling by upgraded TASK3D-a code in preparation of LHD deuterium campaigns

Vincenzi, P.
Primo
;
2015

Abstract

LHD [1] is a superconducting helical device (heliotron type) capable of studying current-less plasmas. Experiments are usually performed with hydrogen (H) plasma, with the majority of heating provided by 5 H neutral beam injectors (NBIs). The use of deuterium (D) is planned in the future LHD campaigns, together with the upgrade of at least 3 NBIs to D injection. In tokamak devices it is already known that the increase of plasma ion mass leads to better confinement properties [2,3]. The presence of isotope effect in helical machines is under investigation and modelling of D helical plasmas can help in the prediction of the confinement properties for future D LHD experiments, and, generally, for extrapolation to helical fusion reactors. Interpretative analyses of the LHD experiments are currently carried out with TASK3D-a integrated transport code [4], capable of treating hydrogen and multi-ion species plasma [5,6]. Effort has been recently put to start the upgrade of TASK3D-a code to extend the analysis capabilities to D plasmas with D NBIs. The present paper introduces the first modifications of the NBI module of TASK3D-a code. The neutral beam ionization code has been improved to consider the injection of D beams in D plasma with various impurities, and a module which estimates the neutron rate production for D-D reactions has been implemented in the code. Both thermal and beam-plasma reactions are taken into account for neutron rate estimation with a simplified approach. This paper critically discusses the first results and benchmarking of the recently updated NBI module of TASK3D-a code for modelling of LHD future D experiments. [1] O. Motojima et al, Nucl. Fusion 40 (2000) 599 [2] J. G. Cordey et al., Plasma Phys. Control. Fusion 42 (2000) A127-A132 [3] H. Urano et al., Nucl. Fusion 52 (2012) 114021 [4] M. Yokoyama et al., Plasma Fusion Res. 8 (2013) 2403016 [5] A. Sakai et al., Plasma Fusion Res. 9, (2014) 3403124 [6] H. Yamaguchi and S. Murakami, Plasma Fusion Res. 9 (2014) 3403127
2015
Istituto per la Scienza e Tecnologia dei Plasmi - ISTP - Sede Secondaria Padova
fusion plasma
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/536799
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