Abstract
BWRs have a radiation shielding wall (RSW) around the reactor pressure vessel (RPV). The RSW has many penetration holes, therefore it is a key-issue to estimate reliably numbers of neutrons leaked through these holes and their spread in drywell cavity surrounded by the primary containment vessel (PCV). To estimate the applicability of the TORT code for this type of streaming geometry, neutron flux distribution in the 1100 MWe BWR that has improved MARK-II type PCV was calculated by TORT using two different models. The contributions of the leakage neutrons to the total neutrons were estimated and the calculated cavity neutron fluxes in the PCV were compared with the measured data. The TORT code was also used to estimate the cavity neutron streaming for another type of PCV, namely MARK-I type 500 MWe/800 MWe BWR plants. The results clarified that the contribution of the leakage neutrons to the total neutrons for 500 MWe, 800 MWe and 1100 MWe plants differed for each other. (author)
Tsukiyama, Toshihisa;
Nemoto, Yuji;
Hayashi, Katsumi;
[1]
Takagi, Masakazu
[2]
- Hitachi, Ltd., Hitachi, Ibaraki (Japan)
- Tokyo Electric Power Co., Inc., Tokyo (Japan)
Citation Formats
Tsukiyama, Toshihisa, Nemoto, Yuji, Hayashi, Katsumi, and Takagi, Masakazu.
Estimation of the RSW neutron streaming using the TORT code.
Japan: N. p.,
2004.
Web.
Tsukiyama, Toshihisa, Nemoto, Yuji, Hayashi, Katsumi, & Takagi, Masakazu.
Estimation of the RSW neutron streaming using the TORT code.
Japan.
Tsukiyama, Toshihisa, Nemoto, Yuji, Hayashi, Katsumi, and Takagi, Masakazu.
2004.
"Estimation of the RSW neutron streaming using the TORT code."
Japan.
@misc{etde_20620309,
title = {Estimation of the RSW neutron streaming using the TORT code}
author = {Tsukiyama, Toshihisa, Nemoto, Yuji, Hayashi, Katsumi, and Takagi, Masakazu}
abstractNote = {BWRs have a radiation shielding wall (RSW) around the reactor pressure vessel (RPV). The RSW has many penetration holes, therefore it is a key-issue to estimate reliably numbers of neutrons leaked through these holes and their spread in drywell cavity surrounded by the primary containment vessel (PCV). To estimate the applicability of the TORT code for this type of streaming geometry, neutron flux distribution in the 1100 MWe BWR that has improved MARK-II type PCV was calculated by TORT using two different models. The contributions of the leakage neutrons to the total neutrons were estimated and the calculated cavity neutron fluxes in the PCV were compared with the measured data. The TORT code was also used to estimate the cavity neutron streaming for another type of PCV, namely MARK-I type 500 MWe/800 MWe BWR plants. The results clarified that the contribution of the leakage neutrons to the total neutrons for 500 MWe, 800 MWe and 1100 MWe plants differed for each other. (author)}
place = {Japan}
year = {2004}
month = {Mar}
}
title = {Estimation of the RSW neutron streaming using the TORT code}
author = {Tsukiyama, Toshihisa, Nemoto, Yuji, Hayashi, Katsumi, and Takagi, Masakazu}
abstractNote = {BWRs have a radiation shielding wall (RSW) around the reactor pressure vessel (RPV). The RSW has many penetration holes, therefore it is a key-issue to estimate reliably numbers of neutrons leaked through these holes and their spread in drywell cavity surrounded by the primary containment vessel (PCV). To estimate the applicability of the TORT code for this type of streaming geometry, neutron flux distribution in the 1100 MWe BWR that has improved MARK-II type PCV was calculated by TORT using two different models. The contributions of the leakage neutrons to the total neutrons were estimated and the calculated cavity neutron fluxes in the PCV were compared with the measured data. The TORT code was also used to estimate the cavity neutron streaming for another type of PCV, namely MARK-I type 500 MWe/800 MWe BWR plants. The results clarified that the contribution of the leakage neutrons to the total neutrons for 500 MWe, 800 MWe and 1100 MWe plants differed for each other. (author)}
place = {Japan}
year = {2004}
month = {Mar}
}