Neutron Yields Based on Transport Calculation in EAST ICRF Minority Heating Plasmas

被引:6
作者
Li Xiaoling [1 ,2 ]
Wan Baonian [1 ]
Guo Zhirong [2 ]
Zhong Guoqiang [1 ]
Hu Liqun [1 ]
Lin Shiyao [1 ]
Zhang Xinjun [1 ]
Ding Siye [1 ]
Lu Bo [1 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
[2] Wuhan Second Ship Design & Res Inst, Wuhan 430064, Peoples R China
基金
中国国家自然科学基金;
关键词
neutron yield; MCNP; ICRF; minority heating; TOKAMAK;
D O I
10.1088/1009-0630/15/5/03
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Neutron diagnostics, including flux and energy spectrum measurements, have been applied on the experimental advanced superconducting tokamak (EAST). The absolute calibration of neutron yields has been achieved by a calculation method using the Monte Carlo automatic modeling (MCAM) system and the Monte Carlo N-Particles (MCNP) code. Since the neutron yield is closely related with the ion density and temperature, it is a good measure of plasma performance, especially the wave heating effect. In ion cyclotron range of frequencies (ICRF) experiments, the increase in the ion temperature derived by the neutron yield indicates an effective plasma heating. Minority protons damp a large fraction of the total wave power, and then transfer part of the energy to deuterium by collisions. Neutron spectrum measurements also indicate that no tail is created by high energy deuterons during ICRF heating. However, the ion temperature derived by the neutron yield is consistent with the result by using a poloidal X-ray imaging crystal spectrometer (PXCS), showing a reliable transport calculation.
引用
收藏
页码:411 / 416
页数:6
相关论文
共 18 条
[1]  
Briesmeister J.F., 2000, MCNP-A general Monte Carlo N -particle transport code, version 4A, V2
[2]  
Hendel H W., 1982, INT SCH PLASMA PHYS, V1
[3]  
HENDRICKS JS, 2004, LAUR040569 LOS AL NA
[4]   Present Status of the EAST Diagnostics [J].
Hu Liqun .
PLASMA SCIENCE & TECHNOLOGY, 2011, 13 (01) :125-128
[5]   Design and analysis of the radiation shield and safety system for HT-7U tokamak [J].
Huang, QY ;
Chai, ZX ;
Chen, YX ;
Wu, YC ;
Chen, CB ;
Kong, MH .
FUSION ENGINEERING AND DESIGN, 2003, 69 (1-4) :749-756
[6]   NEUTRON MEASUREMENT TECHNIQUES FOR TOKAMAK PLASMAS [J].
JARVIS, ON .
PLASMA PHYSICS AND CONTROLLED FUSION, 1994, 36 (02) :209-244
[7]   Neutron flux in lower hybrid current drive plasmas on EAST [J].
Li, X. L. ;
Wan, B. N. ;
Zhong, G. Q. ;
Xu, P. ;
Qian, J. P. ;
Shan, J. F. ;
Wang, M. ;
Ding, B. J. ;
Shi, Y. J. ;
Yang, Y. ;
Zha, W. Q. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2010, 52 (10)
[8]   UNFOLDING ACTIVATION AND MULTISPHERE DETECTOR DATA [J].
ROUTTI, JT ;
SANDBERG, JV .
RADIATION PROTECTION DOSIMETRY, 1985, 10 (1-4) :103-110
[9]   Imaging x-ray crystal spectrometer on EAST [J].
Shi, Yuejiang ;
Wang, Fudi ;
Wan, Baonian ;
Bitter, Manfred ;
Lee, Sanggon ;
Bak, Jungyo ;
Hill, Kennith ;
Fu, Jia ;
Li, Yingying ;
Zhang, Wei ;
Ti, Ang ;
Ling, Bili .
PLASMA PHYSICS AND CONTROLLED FUSION, 2010, 52 (08)
[10]  
Stix T.H., 1992, Waves in plasmas