Abstract
Two different types of the CANDU fuel bundles have been modeled for the ASSERT-IV code subchannel analysis. From calculated values of mixture enthalpy and void fraction distribution in the fuel bundles, it is found that net buoyancy effect is pronounced in the central region of the DUPIC fuel bundle when compared with the standard CANDU fuel bundle. It is also found that the central region of the DUPIC fuel bundle can be cooled more efficiently than that of the standard fuel bundle. From the calculated mixture enthalpy distribution at the exit of the fuel channel, it is found that the mixture enthalpy and void fraction can be highest in the peripheral region of the DUPIC fuel bundle. On the other hand, the enthalpy and the void fraction were found to be highest in the central region of the standard CANDU fuel bundle at the exit of the fuel channel. This study shows that the subchannel analysis is very useful in assessing thermal behavior of the fuel bundle that could be used in CANDU reactors. 10 refs., 4 figs., 2 tabs. (Author)
Park, J W;
Choi, H;
Rhee, B W
[1]
- Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Citation Formats
Park, J W, Choi, H, and Rhee, B W.
Enthalpy and void distributions in subchannels of PHWR fuel bundles.
Korea, Republic of: N. p.,
1998.
Web.
Park, J W, Choi, H, & Rhee, B W.
Enthalpy and void distributions in subchannels of PHWR fuel bundles.
Korea, Republic of.
Park, J W, Choi, H, and Rhee, B W.
1998.
"Enthalpy and void distributions in subchannels of PHWR fuel bundles."
Korea, Republic of.
@misc{etde_325258,
title = {Enthalpy and void distributions in subchannels of PHWR fuel bundles}
author = {Park, J W, Choi, H, and Rhee, B W}
abstractNote = {Two different types of the CANDU fuel bundles have been modeled for the ASSERT-IV code subchannel analysis. From calculated values of mixture enthalpy and void fraction distribution in the fuel bundles, it is found that net buoyancy effect is pronounced in the central region of the DUPIC fuel bundle when compared with the standard CANDU fuel bundle. It is also found that the central region of the DUPIC fuel bundle can be cooled more efficiently than that of the standard fuel bundle. From the calculated mixture enthalpy distribution at the exit of the fuel channel, it is found that the mixture enthalpy and void fraction can be highest in the peripheral region of the DUPIC fuel bundle. On the other hand, the enthalpy and the void fraction were found to be highest in the central region of the standard CANDU fuel bundle at the exit of the fuel channel. This study shows that the subchannel analysis is very useful in assessing thermal behavior of the fuel bundle that could be used in CANDU reactors. 10 refs., 4 figs., 2 tabs. (Author)}
place = {Korea, Republic of}
year = {1998}
month = {Dec}
}
title = {Enthalpy and void distributions in subchannels of PHWR fuel bundles}
author = {Park, J W, Choi, H, and Rhee, B W}
abstractNote = {Two different types of the CANDU fuel bundles have been modeled for the ASSERT-IV code subchannel analysis. From calculated values of mixture enthalpy and void fraction distribution in the fuel bundles, it is found that net buoyancy effect is pronounced in the central region of the DUPIC fuel bundle when compared with the standard CANDU fuel bundle. It is also found that the central region of the DUPIC fuel bundle can be cooled more efficiently than that of the standard fuel bundle. From the calculated mixture enthalpy distribution at the exit of the fuel channel, it is found that the mixture enthalpy and void fraction can be highest in the peripheral region of the DUPIC fuel bundle. On the other hand, the enthalpy and the void fraction were found to be highest in the central region of the standard CANDU fuel bundle at the exit of the fuel channel. This study shows that the subchannel analysis is very useful in assessing thermal behavior of the fuel bundle that could be used in CANDU reactors. 10 refs., 4 figs., 2 tabs. (Author)}
place = {Korea, Republic of}
year = {1998}
month = {Dec}
}