Abstract
As a preliminary step for the design of the neutron diagnostics in the IGNITOR tokamak, the overall neutron field in the device was calculated with the help of the MCNP code, which solves, with the Monte Carlo method, neutron and photon transport problems in arbitrary 3-D geometries. The poloidal distribution of the fluxes on the first wall and the related energy spectra were calculated to estimate the backscattered contribution to signals at spectrometers and collimated detectors for measurements with spatial resolution in the plasma. The average fluxes on the top and the lateral cryostat surfaces, and the local fluxes on the equatorial plane outside the cryostat wall, were also calculated in order to determine the neutron counter characteristics and expected performance. The accuracy of the numerical simulation and of the modeling of the IGNITOR device adopted in this work, already allows for the calibrations of the activation system, that should be used as an independent method for the absolute measurement of the total neutron yield and for more general calculations concerning the activation of structural materials and for safety.
Citation Formats
Batistoni, P, and Rollet, S.
Neutron transport for Ignitor neutron diagnostics.
Italy: N. p.,
1992.
Web.
Batistoni, P, & Rollet, S.
Neutron transport for Ignitor neutron diagnostics.
Italy.
Batistoni, P, and Rollet, S.
1992.
"Neutron transport for Ignitor neutron diagnostics."
Italy.
@misc{etde_10147254,
title = {Neutron transport for Ignitor neutron diagnostics}
author = {Batistoni, P, and Rollet, S}
abstractNote = {As a preliminary step for the design of the neutron diagnostics in the IGNITOR tokamak, the overall neutron field in the device was calculated with the help of the MCNP code, which solves, with the Monte Carlo method, neutron and photon transport problems in arbitrary 3-D geometries. The poloidal distribution of the fluxes on the first wall and the related energy spectra were calculated to estimate the backscattered contribution to signals at spectrometers and collimated detectors for measurements with spatial resolution in the plasma. The average fluxes on the top and the lateral cryostat surfaces, and the local fluxes on the equatorial plane outside the cryostat wall, were also calculated in order to determine the neutron counter characteristics and expected performance. The accuracy of the numerical simulation and of the modeling of the IGNITOR device adopted in this work, already allows for the calibrations of the activation system, that should be used as an independent method for the absolute measurement of the total neutron yield and for more general calculations concerning the activation of structural materials and for safety.}
place = {Italy}
year = {1992}
month = {Mar}
}
title = {Neutron transport for Ignitor neutron diagnostics}
author = {Batistoni, P, and Rollet, S}
abstractNote = {As a preliminary step for the design of the neutron diagnostics in the IGNITOR tokamak, the overall neutron field in the device was calculated with the help of the MCNP code, which solves, with the Monte Carlo method, neutron and photon transport problems in arbitrary 3-D geometries. The poloidal distribution of the fluxes on the first wall and the related energy spectra were calculated to estimate the backscattered contribution to signals at spectrometers and collimated detectors for measurements with spatial resolution in the plasma. The average fluxes on the top and the lateral cryostat surfaces, and the local fluxes on the equatorial plane outside the cryostat wall, were also calculated in order to determine the neutron counter characteristics and expected performance. The accuracy of the numerical simulation and of the modeling of the IGNITOR device adopted in this work, already allows for the calibrations of the activation system, that should be used as an independent method for the absolute measurement of the total neutron yield and for more general calculations concerning the activation of structural materials and for safety.}
place = {Italy}
year = {1992}
month = {Mar}
}