Neutron Diagnostics for the Energetic Ion Transport Analysis
Author:
Affiliation:
1. Japan Atomic Energy Research Institute
2. National Institute of Fusion Science
Publisher
Japan Society of Plasma Science and Nuclear Fusion Research
Link
http://www.jstage.jst.go.jp/article/jspf/80/10/80_10_860/_pdf
Reference58 articles.
1. Improved formulas for fusion cross-sections and thermal reactivities
2. Confinement and heating of a deuterium-tritium plasma
3. Fusion power production from TFTR plasmas fueled with deuterium and tritium
4. High fusion performance from deuterium-tritium plasmas in JET
5. Fusion reactivities and power multiplication factors of beam-driven toroidal reactors with both D and T injection
Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. Operation Control and Diagnostic Systems;Fusion Reactor Design;2021-11-12
2. Modification of Neutron Emission Spectra and Determination of Fuel Ion Ratio in Beam-Injected Deuterium-Tritium Plasma;Plasma and Fusion Research;2016
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