In-vessel design of ITER diagnostic neutron activation system.
A neutron activation system utilizing an encapsulated metal sample technique will be implemented to evaluate total fusion power from ITER plasma. The positions of seven irradiation ends for each poloidal section are determined to optimize the measurements from asymmetric, elongated plasma with minimum uncertainty. To determine the exact location of the irradiation end, some physical and technical aspects for each location are investigated. Monte Carlo neutronic calculations are performed to assess the physical characteristics and optimize the design of each irradiation end.
Cheon
M S
MS
National Fusion Research Institute, Yuseong-gu, Deajeon 305-333, Republic of Korea.
Pak
S
S
Lee
H G
HG
Bertalot
L
L
Walker
C
C