Fig 13 - uploaded by Arkady Serikov
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Local SDDR (Sv/h) map with contour lines plotted on radial-vertical (X-Z) central (Y = 0) cut of the MCNP model with fully shielded Diagnostic Generic Equatorial Port Plug (DGEPP) at 12 days after shutdown -the plot covers the same area of the MCNP model as in Fig. 12.
Source publication
The neutronic analysis results presented in this paper support the design development of the Edge Charge Exchange Recombination Spectroscopy (CXRS-Edge) system to be installed in Equatorial Port #3 (EP3) of ITER. That is an active optical diagnostic system with a dogleg labyrinth design of two optical pathways and a system of mirrors arranged in Di...
Citations
The radial neutron camera (RNC) is a key ITER diagnostic system designed to measure the uncollided 14- and 2.5-MeV neutrons from deuterium–tritium (DT) and deuterium–deuterium (DD) fusion reactions, through an array of detectors covering a full poloidal plasma section along collimated lines of sight (LoS). Its main objective is the assessment of the neutron emissivity/
$\alpha $
source profile and the total neutron source strength, providing spatially resolved measurements of several parameters needed for fusion power estimation, plasma control, and plasma physics studies. The present RNC layout is composed of two fan-shaped collimating structures viewing the plasma radially through vertical slots in the diagnostic shielding module (DSM) of ITER Equatorial Port 1 (EP01): the ex-port subsystem and the in-port one. The ex-port subsystem, devoted to the plasma core coverage, extends from the Port Interspace to the Bioshield Plug: it consists of a massive shielding unit hosting two sets of collimators lying on different toroidal planes, leading to a total of 16 interleaved LoS. The in-port system consists of a cassette, integrated inside the port plug DSM, containing two detectors per each of the six LoS looking at the plasma edges. The in-port system must guarantee the required measurement performances in critical operating conditions in terms of high radiation levels, given its proximity to the plasma neutron source. This article presents an updated neutronic analysis based on the latest design of the in-port system and port plug. It has been performed by means of the Monte Carlo MCNP code and provides nuclear loads on the in-port RNC during normal operating conditions (NOC) and inputs for the measurement performance analysis.
The three-wave based laser polarimeter/interferometer and the CO2 laser dispersion interferometer are used to determine the electron and current density profiles on Chinese fusion engineering test reactor (CFETR). Radiation shielding is designed for the combination of polarimeter/interferometer and CO2 dispersion interferometer. Furthermore, neutronics models of two systems are developed based on the engineering integrated design of CFETR polarimeter/interferometer and CO2 dispersion interferometer and the major material components of CFETR. The polarimeter/interferometer and CO2 dispersion interferometer’s neutron and photon transport simulations were performed using the Monte Carlo neutral transport code (MCNP) to determine the energy deposition and neutron energy spectrum of the optical mirrors. The energy deposition of the first mirrors on the polarimeter/interferometer are reduced by three orders with the whole shielding. Since the mirrors of CO2 dispersion interferometer are very close to the diagnostic first wall (DFW), shielding space is limit, the CO2 dispersion interferometer energy deposition is higher than that of the polarimeter/interferometer. The dose rate after shutdown 106 s in the back drawer structure has been estimated to be 83 μSv/h when the radiation shield is filled in the diagnostic shielding modules (DSM), which is below the design threshold of 100 μSv/h. Radiation shielding design plays a key role in successful applying polarimeter/interferometer and CO2 dispersive interferometer in CFETR.
