@article{oai:nifs-repository.repo.nii.ac.jp:00010731,
 author = {ISOBE,  Mitsutaka and OGAWA,  Kunihoro and Nishitani, Takeo and PU, Neng and Kawase, Hiroki and SEKI,  Ryosuke and NUGA, Hideo and TAKADA, Eiji and MURAKAMI,  Sadayoshi and SUZUKI,  Yasuhiro and YOKOYAMA,  Masayuki and OSAKABE,  Masaki and LHD, Experiment Group},
 issue = {8},
 journal = {Nuclear Fusion},
 month = {Jun},
 note = {0000-0002-3572-1882, The deuterium operation of the large helical device (LHD) heliotron started in March 7, 2017, after long-term preparation and commissioning works necessary to execute the deuterium experiment. A comprehensive set of neutron diagnostics was implemented to accelerate energetic-particle physics research in the LHD. The calibrated ex-vessel neutron flux monitor indicated that the total neutron emission rate in the first deuterium campaign reached 3.3  ×  1015 n s−1 in inward shifted magnetic field configuration where confinement of helically trapped energetic ions is predicted to be better. Density dependence of measured total neutron emission rate was consistent with that predicted by the calculation. The neutron decay rate analysis following perpendicular deuterium beam blips injection suggested that the confinement of helically trapped beam ions can be understood by the classical slowing down model in relatively high-electron density plasmas at inward shifted magnetic field configuration. On the other hand, loss of helically-trapped beam ions was recognized even in the inward shifted configuration in the case of low density. Performance of the vertical neutron camera was verified by changing the plasma position and/or magnetic field strength. Drastic change of neutron emission profile was observed when the resistive interchange mode driven by helically-trapped beam ions appears. It was successfully demonstrated that the vertical neutron camera can play an important role in revealing radial transport and/or loss of beam ions. Triton burnup study was also conducted. In the first deuterium campaign, the maximum triton burnup ratio of 0.45% was obtained in inward shifted configuration. The burnup ratio decreased as a plasma was shifted outwardly as expected.},
 title = {Fusion neutron production with deuterium neutral beam injection and enhancement of energetic-particle physics study in the Large Helical Device},
 volume = {58},
 year = {2018}
}