Neutron diagnostics for ITER

Journal Article · Wed Jan 01 04:00:00 EST 1997 · Review of Scientific Instruments

DOI:https://doi.org/10.1063/1.1147906· OSTI ID:451805

Johnson, L C; Barnes, C W; Krasilnikov, A; Marcus, F B; Nishitani, T ^[1]

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1. ITER San Diego Joint Work Site, La Jolla, California 92037 (United States)

Neutron diagnostics will play a prominent role in the control and evaluation of thermonuclear plasmas in ignition device to test engineering concepts (ITER). As in present D-T experiments, measurements of neutron yield and of fusion power and power density are essential. In addition, the spectral width of the 14.1-MeV t(d,n){alpha} neutron emission should be a reliable indicator of ion temperature in an ignited plasma. More detailed measurements of the neutron spectrum may allow determination of the densities of tritium, deuterium, and confined alpha particles. Although the central fusion power density in ITER will be comparable to the maximum values obtainable in TFTR and JET, neutron flux on the first wall will be ten times higher, and the neutron yield per discharge will be about five orders of magnitude greater than previously experienced. The thermal and radiation shielding necessary to protect the ITER superconducting coils from the intense flux at the first wall will restrict diagnostic access for neutron cameras and spectrometers, complicate the design of material activation systems, and limit the applicability of conventional calibration techniques for neutron source strength monitors. These considerations, together with unprecedented reliability requirements and the need for full remote handling of many components, pose demanding challenges for the design of the ITER neutron diagnostic systems. {copyright} {ital 1997 American Institute of Physics.}

• OSTI ID: 451805
• Report Number(s): CONF-960543--
• Journal Information: Review of Scientific Instruments, Journal Name: Review of Scientific Instruments Journal Issue: 1 Vol. 68; ISSN 0034-6748; ISSN RSINAK
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ACCURACY
ACTIVATION ANALYSIS
D-T REACTORS
ITER TOKAMAK
MEV RANGE 10-100
NEUTRON DETECTION
NEUTRON FLUX
NEUTRON SPECTROMETERS
PLASMA DIAGNOSTICS
SPATIAL RESOLUTION
TIME RESOLUTION
TOKAMAK DEVICES
fusion reactor ignition
fusion reactor instrumentation
plasma temperature
plasma toroidal confinement