Abstract
For a 3-loop plant, a new reactivity model which is easily applicable in evaluating the safety of hot zero power steamline break accident was established. The applicability of this reactivity model for a 2-loop plant has been examined. As per the result, the weighting for the core inlet average density is optimized to be 0.8 and 0.2 respectively for each of a cold and a hot loop. Also, it is verified that the safety analysis reactivity coefficients suggested in this model are enoughly conservative as compared with the best-estimated reactivity coefficients. These results demonstrate that the established reactivity model for a 3-loop plant is applicable to a 2-loop plant. (Author).
Um, Kil Sup;
Kim, Hee Cheol;
Jung, Yil Sup;
Park, Jong Ryul;
Lee, Chong Chul;
Paek, Ju Hyun;
Zee, Sung Kyun
[1]
- Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Citation Formats
Um, Kil Sup, Kim, Hee Cheol, Jung, Yil Sup, Park, Jong Ryul, Lee, Chong Chul, Paek, Ju Hyun, and Zee, Sung Kyun.
Reactivity coefficients model for the steamline break accidents (2 loop plant).
Korea, Republic of: N. p.,
1992.
Web.
Um, Kil Sup, Kim, Hee Cheol, Jung, Yil Sup, Park, Jong Ryul, Lee, Chong Chul, Paek, Ju Hyun, & Zee, Sung Kyun.
Reactivity coefficients model for the steamline break accidents (2 loop plant).
Korea, Republic of.
Um, Kil Sup, Kim, Hee Cheol, Jung, Yil Sup, Park, Jong Ryul, Lee, Chong Chul, Paek, Ju Hyun, and Zee, Sung Kyun.
1992.
"Reactivity coefficients model for the steamline break accidents (2 loop plant)."
Korea, Republic of.
@misc{etde_10112974,
title = {Reactivity coefficients model for the steamline break accidents (2 loop plant)}
author = {Um, Kil Sup, Kim, Hee Cheol, Jung, Yil Sup, Park, Jong Ryul, Lee, Chong Chul, Paek, Ju Hyun, and Zee, Sung Kyun}
abstractNote = {For a 3-loop plant, a new reactivity model which is easily applicable in evaluating the safety of hot zero power steamline break accident was established. The applicability of this reactivity model for a 2-loop plant has been examined. As per the result, the weighting for the core inlet average density is optimized to be 0.8 and 0.2 respectively for each of a cold and a hot loop. Also, it is verified that the safety analysis reactivity coefficients suggested in this model are enoughly conservative as compared with the best-estimated reactivity coefficients. These results demonstrate that the established reactivity model for a 3-loop plant is applicable to a 2-loop plant. (Author).}
place = {Korea, Republic of}
year = {1992}
month = {Sep}
}
title = {Reactivity coefficients model for the steamline break accidents (2 loop plant)}
author = {Um, Kil Sup, Kim, Hee Cheol, Jung, Yil Sup, Park, Jong Ryul, Lee, Chong Chul, Paek, Ju Hyun, and Zee, Sung Kyun}
abstractNote = {For a 3-loop plant, a new reactivity model which is easily applicable in evaluating the safety of hot zero power steamline break accident was established. The applicability of this reactivity model for a 2-loop plant has been examined. As per the result, the weighting for the core inlet average density is optimized to be 0.8 and 0.2 respectively for each of a cold and a hot loop. Also, it is verified that the safety analysis reactivity coefficients suggested in this model are enoughly conservative as compared with the best-estimated reactivity coefficients. These results demonstrate that the established reactivity model for a 3-loop plant is applicable to a 2-loop plant. (Author).}
place = {Korea, Republic of}
year = {1992}
month = {Sep}
}