Abstract
The calculations were performed using both the Monte Carlo code MCNP and the 2D discrete ordinates neutron/{gamma} transport code DORT. Consistent nuclear data were used: For the Monte Carlo calculations data were taken from the EFF-1.3 library, for the discrete ordinates calculations data were taken from the MAT175 library. Both libraries are based on the JEF/EFF-1 evaluation. Care was taken to model the 2.0 cm wide gaps between two blanket segments, as the neutron flux behind the vacuum vessel is largely determined by neutrons streaming through these gaps. The resulting neutron- and {gamma}-flux spectra are in excellent agreement up to the end of the cryostat. It is noted, that at this position the attenuation of the neutron flux is about 11 orders of magnitude. Due to precautions in the Monte Carlo calculations the uncertainty in neutron- and {gamma}-flux spectra calculated by MCNP is only small: The uncertainty in the integrated neutron spectrum amounts to approximately 15% at the end of the cryostat. Also the dose-rates as calculated by MCNP and DORT agree well. Differences occur when heating data are compared. This is clearly due to the different way in which nuclear heating is treated in MCNP (direct calculation of heating)
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Citation Formats
Hogenbirk, A, and Verschuur, K A.
Calculation of radiation fields inside and outside the NET cryostat/biological shield during operation.
Netherlands: N. p.,
1993.
Web.
Hogenbirk, A, & Verschuur, K A.
Calculation of radiation fields inside and outside the NET cryostat/biological shield during operation.
Netherlands.
Hogenbirk, A, and Verschuur, K A.
1993.
"Calculation of radiation fields inside and outside the NET cryostat/biological shield during operation."
Netherlands.
@misc{etde_10142607,
title = {Calculation of radiation fields inside and outside the NET cryostat/biological shield during operation}
author = {Hogenbirk, A, and Verschuur, K A}
abstractNote = {The calculations were performed using both the Monte Carlo code MCNP and the 2D discrete ordinates neutron/{gamma} transport code DORT. Consistent nuclear data were used: For the Monte Carlo calculations data were taken from the EFF-1.3 library, for the discrete ordinates calculations data were taken from the MAT175 library. Both libraries are based on the JEF/EFF-1 evaluation. Care was taken to model the 2.0 cm wide gaps between two blanket segments, as the neutron flux behind the vacuum vessel is largely determined by neutrons streaming through these gaps. The resulting neutron- and {gamma}-flux spectra are in excellent agreement up to the end of the cryostat. It is noted, that at this position the attenuation of the neutron flux is about 11 orders of magnitude. Due to precautions in the Monte Carlo calculations the uncertainty in neutron- and {gamma}-flux spectra calculated by MCNP is only small: The uncertainty in the integrated neutron spectrum amounts to approximately 15% at the end of the cryostat. Also the dose-rates as calculated by MCNP and DORT agree well. Differences occur when heating data are compared. This is clearly due to the different way in which nuclear heating is treated in MCNP (direct calculation of heating) and DORT (kerma factors used; including radioactive decay contributions). (orig.)}
place = {Netherlands}
year = {1993}
month = {Sep}
}
title = {Calculation of radiation fields inside and outside the NET cryostat/biological shield during operation}
author = {Hogenbirk, A, and Verschuur, K A}
abstractNote = {The calculations were performed using both the Monte Carlo code MCNP and the 2D discrete ordinates neutron/{gamma} transport code DORT. Consistent nuclear data were used: For the Monte Carlo calculations data were taken from the EFF-1.3 library, for the discrete ordinates calculations data were taken from the MAT175 library. Both libraries are based on the JEF/EFF-1 evaluation. Care was taken to model the 2.0 cm wide gaps between two blanket segments, as the neutron flux behind the vacuum vessel is largely determined by neutrons streaming through these gaps. The resulting neutron- and {gamma}-flux spectra are in excellent agreement up to the end of the cryostat. It is noted, that at this position the attenuation of the neutron flux is about 11 orders of magnitude. Due to precautions in the Monte Carlo calculations the uncertainty in neutron- and {gamma}-flux spectra calculated by MCNP is only small: The uncertainty in the integrated neutron spectrum amounts to approximately 15% at the end of the cryostat. Also the dose-rates as calculated by MCNP and DORT agree well. Differences occur when heating data are compared. This is clearly due to the different way in which nuclear heating is treated in MCNP (direct calculation of heating) and DORT (kerma factors used; including radioactive decay contributions). (orig.)}
place = {Netherlands}
year = {1993}
month = {Sep}
}