Neutronic analysis of the Diagnostic Equatorial Ports in ITER

Suárez, Alejandro; Bertalot, L.; Maquet, P.; Pitcher, C.S.; Portales, M.; Serikov, A.; Udintsev, V. S.; Walsh, Michael J.

doi:10.1016/j.fusengdes.2015.06.091

Cited by 13 publications

(3 citation statements)

References 5 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The situation in the ITER EPs is particularly challenging, due to their proximity to the plasma, the port plug weight restrictions, the limited space for shielding and the relative orientation with respect to the plasma. A collection of works showing current status is [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15][16].…”

Section: Introductionmentioning

confidence: 99%

“…Large efforts to reduce the SDDR in the ITER port interspaces have been devoted to improve the design of the port plugs as understood from works [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15][16]. In example, for Diagnostics port plugs, works to develop a long diagnostics shield module (DSM) for a satisfactory port plug integration are in progress [17].…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Scoping studies of shielding to reduce the shutdown dose rates in the ITER ports

et al. 2018

View full text Add to dashboard Cite

The planned in situ maintenance tasks in the ITER port interspace are fundamental to ensure the operation of equipment to control, evaluate and optimize the plasma performance during the entire facility lifetime. They are subject to a limit of shutdown dose rates (SDDR) of 100 µSv h−1 after 106 s of cooling time, which is nowadays a design driver for the port plugs as well as the application of ALARA. Three conceptual shielding proposals outside the ITER ports are studied in this work to support the achievement of this objective. Considered one by one, they offer reductions ranging from 25% to 50%, which are rather significant. This paper shows that, by combining these shields, the SDDR as low as 57Δ µSv h−1 can be achieved with a local approach considering only radiation from one port (no cross-talk form neighboring ports). The locally evaluated SDDR are well below the limit which is an essential pre-requisite for achieving 100µSv h−1 in a global analysis including all contributions. Further studies will have to deal with a realistic port plug design and the cross-talks from neighbour ports.

show abstract

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Scoping studies of shielding to reduce the shutdown dose rates in the ITER ports

et al. 2018

View full text Add to dashboard Cite

show abstract

“…Neutronic analyses have being done alongside the design work for ITER port plugins and diagnostics in the port, to guarantee the functionality of diagnostic detectors, as well as the nuclear safety for maintenance personnel. These works include the radiation load and shutdown dose rate analyses for diagnostic equatorial port plug (EPP) and the electron cyclotron heating upper launcher with the Monte Carlo N-particle transport code (MCNP) and the inventory code FISPACT [1,2], at ITER Organization, Karlsruhe Institute of Technology, Culham Centre for Fusion Energy and the other institutes.…”

Section: Introductionmentioning

confidence: 99%

Neutronic analysis of ITER radial x-ray camera

Niu¹,

Cao²,

Xu³

2018

Plasma Sci. Technol.

View full text Add to dashboard Cite

The radial x-ray camera (RXC) is designed to measure the poloidal profile of plasma x-ray emission with high spatial and temporal resolution. The RXC diagnostic system consists of internal camera module and external camera module that view the core region and outer region through the vertical slots of the diagnostic first wall and diagnostics shield module of the equatorial port plug. To ensure the normal performance of the silicon photodiode array detectors of the cameras in the hard neutron irradiation environment in ITER tokamak, it is necessary to calculate neutron flux, radiation damage and the nuclear heating of the silicon photodiode array detectors and simulate the radiation maps of the range of RXC. This work estimated the nuclear environment of RXC based on Monte Carlo N-particle transport code, plasma scenarios of ITER tokamak and the RXC-integrated ITER CLITE model. The neutron flux of silicon photodiode array detectors and the lifetime of the silicon photodiode detector in the camera were calculated. The neutronic analysis results show that the shielding design has achieved the effect as expected and is able to guarantee the normal work of the detector during the ITER deuterium-deuterium phase without replacement, three detectors of the external camera can be operated during the whole deuterium-tritium phase without replacement.

show abstract