Journal Article10.1063/1.1141558
Neutron calibration techniques for comparison of tokamak results
J. D. Strachan,J. M. Adams,Cris W. Barnes,P. Batistoni,Hans-Stephan Bosch,J. S. Brzosko,A.C. England,C.L. Fiore,R. S. Granetz,H. W. Hendel,F. Hoenen,O. N. Jarvis,D. L. Jassby,L. P. Ku,P. Liu,G. Martin,S. McCauley,R. W. Motley,Takeo Nishitani,B. V. Robouch,T. Saito,Mamiko Sasao,R. D. Stav,P. L. Taylor +23 more
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TL;DR: In this paper, the authors present details on detector positioning, neutron transport calculations, and interlab normalization needed to accomplish the standardized calibration using a Cf neutron source, and discuss the suitability of two techniques: (1) a 252Cf source calibration of epithermal neutron detectors, and (2) threshold neutron activation of Ni foils placed vertically above or below the plasma.
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Abstract: A workshop on 1–3 August 1989 reviewed the techniques, uncertainties, and experiences of neutron calibration on PLT, TFTR, JET, Tore Supra, JT‐60, JIPPT‐IIU, Alcator C‐Mod, ATF, FT, ASDEX, Textor, and DIII‐D. In the summary session, the workshop participants discussed possible consensus neutron calibration techniques appropriate to D‐D plasmas in tokamaks. The application of such techniques would facilitate a more accurate comparison of neutron yields from different devices, and also allow new calibration techniques to relate their precision to a reference value. General agreement was reached on the suitability of two techniques: (1) a 252Cf source calibration of epithermal neutron detectors, and (2) threshold neutron activation of Ni foils placed vertically above or below the plasma. This paper will present details on detector positioning, neutron transport calculations, and interlab normalization needed to accomplish the standardized calibration using a Cf neutron source.
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Citations
Results from deuterium-tritium tokamak confinement experiments
TL;DR: In this article, the technical and scientific results from deuterium-tritium experiments on the Joint European Torus (JET) and the Tokamak Fusion Test Reactor (TFTR) are reviewed, with particular emphasis on alpha-particle physics issues.
Absolute calibration of the JT‐60U neutron monitors using a 252Cf neutron sourcea)
Takeo Nishitani,Hiroshi Takeuchi,Takashi Kondoh,T. Itoh,Masaaki Kuriyama,Yujiro Ikeda,T. Iguchi,Cris W. Barnes +7 more
TL;DR: In this article, the in situ calibration was performed by moving the 252Cf neutron source toroidally through the JT•60 vacuum vessel, and the total detection efficiency for the torus neutron source was obtained by averaging the point efficiencies over the whole toroidal angle.
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Wide dynamic range neutron flux monitor having fast time response for the Large Helical Device.
Mitsutaka Isobe,Kunihiro Ogawa,Hitoshi Miyake,Hiroshi Hayashi,T. Kobuchi,Y. Nakano,Kenichi Watanabe,Akira Uritani,Tsuyoshi Misawa,Takeo Nishitani,Makoto Tomitaka,T. Kumagai,Y. Mashiyama,Daijiro Ito,Shigehiro Kono,Michinori Yamauchi,Yasuhiko Takeiri,Yasuhiko Takeiri +17 more
TL;DR: A fast time response, wide dynamic range neutron flux monitor has been developed toward the LHD deuterium operation by using leading-edge signal processing technologies providing maximum counting rate up to ∼5 × 10(9) counts/s.
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Fusion neutron production with deuterium neutral beam injection and enhancement of energetic-particle physics study in the large helical device
Mitsutaka Isobe,Mitsutaka Isobe,Kunihiro Ogawa,Kunihiro Ogawa,Takeo Nishitani,Neng Pu,Hiroki Kawase,Ryosuke Seki,Ryosuke Seki,H. Nuga,Eiji Takada,Sadayoshi Murakami,Yasuhiro Suzuki,Yasuhiro Suzuki,Masayuki Yokoyama,Masayuki Yokoyama,Masaki Osakabe,Masaki Osakabe +17 more
Abstract: 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.
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A full and heterogeneous model of the ITER tokamak for comprehensive nuclear analyses
Rafael Juarez,G. Pedroche,Michael Loughlin,Raul Pampin,P. Martinez,M. De Pietri,J. Alguacil,Francisco Ogando,Patrick Sauvan,A.J. Lopez-Revelles,A. Kolsek,E. Polunovskiy,Marco Fabbri,Javier Sanz +13 more
TL;DR: In this paper, the authors present a detailed and realistic 360° MCNP model of the ITER tokamak called E-lite, which solves previously intractable problems with marked benefits for the future nuclear analysis of ITER, with applications to DEMO and future reactors.
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References
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TL;DR: In this article, a fusion neutron emission of 1.5 × 1014 neutrons s−1 and 2 × 1013 neutrons/pulse has been observed for PLT deuterium discharges with up to 2.5 MW of neutral-beam injection.
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Neutron flux measurements around the Princeton large tokamak
TL;DR: Using indium activation foils, the toroidal and poloidal neutron emission patterns for PLT plasmas which include ICRF and neutral beam heating were determined by counting the 336 keV γ-line of the 115mIn decay as discussed by the authors.
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Calibration of the TFTR neutron activation system
TL;DR: In this paper, both D-D and D-T neutrons were used to calibrate the TFTR neutron activation (NA) system for point sources located within the tokamak.
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TFTR epithermal neutron detector system: Recalibration and effect of nonisotropic neutron emission
H. W. Hendel,D. L. Jassby,Hans-Stephan Bosch,Cris W. Barnes,L. C. Johnson,Thomas J. Murphy,E. B. Nieschmidt,T. Saito,J. D. Strachan,G. D. Tait,K. M. Young +10 more
TL;DR: In this paper, the primary TFTR neutron source strength measurement system consists of seven fission detectors previously calibrated with D-D and D-T neutron generators and a 252Cf neutron source inside the TFTR vacuum vessel.
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Studies of neutron emission during the start-up phase of the Alcator C tokamak
TL;DR: Alcator C operations commenced with discharge cleaning and tokamak operation using hydrogen filling gas as discussed by the authors, which resulted in dosimeter readings of a few roentgen per shot in the vicinity of the limiter and a localized source of neutron emission of up to 109 neutrons per shot which were subsequently identified as having photonuclear origin.