Published March 2006 | Version v1
Journal article Metadata-only

Fusion neutron yield and flux calculation on HT-7 superconducting tokamak

Creators

  • 1. Chinese Academy of Sciences, Hefei (China). Inst. of Plasma Physics

Description

Neutron yield and flux have been numerically estimated on HT-7 tokamak. The total fusion neutron yield and neutron flux distribution on different positions and azimuth angles of the device are presented. Analyses on the errors induced by ion temperature and density distribution factors are given in detail. The results of the calculations provide a useful database for neutron diagnostics and neutron radiation protection. (authors)

Additional details

Publishing Information

Journal Title
Chinese Journal of Nuclear Science and Engineering
Journal Volume
26
Journal Issue
1
Journal Page Range
p. 28-32, 38
ISSN
0258-0918

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
37110745
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
DENSITY; DISTRIBUTION; ERRORS; FUSION YIELD; HT-7 TOKAMAK; ION TEMPERATURE; NEUTRON FLUX; NEUTRONS; PLASMA; RADIATION PROTECTION; SUPERCONDUCTING MAGNETS; THREE-DIMENSIONAL CALCULATIONS
Descriptors DEC
BARYONS; CLOSED PLASMA DEVICES; ELECTRICAL EQUIPMENT; ELECTROMAGNETS; ELEMENTARY PARTICLES; EQUIPMENT; FERMIONS; HADRONS; MAGNETS; NUCLEAR REACTION YIELD; NUCLEONS; PHYSICAL PROPERTIES; RADIATION FLUX; SUPERCONDUCTING DEVICES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; YIELDS

Optional Information

Notes
8 figs., 1 tab., 9 refs.