Abstract
This paper presents the results of a comparison of the analyses of a postulated Loss of Coolant Accident (LOCA) in Pickering NGS A reactors using the two neutron kinetics codes SMOKIN and CERBERUS. Both codes have been used to simulate the space-time neutronic behaviour of CANDU-PHWR reactors. The main objective of the present study is to evaluate the accuracy with which SMOKIN can predict power transients compared to CERBERUS. The comparison shows that the two codes produce similar bulk power and reactivity transients. However, SMOKIN was found to overestimate the power transient (relative to CERBERUS) in some regions of the core, which is indicative of the spatial differences between the two codes. It was demonstrated that part of this overestimate is due to the use of reaction-rate averaged fuel properties in SMOKIN, compared to instantaneous fuel properties in CERBERUS. (author). 5 refs., 3 tabs., 6 figs.
Younis, M H;
[1]
Gaboury, G
[2]
- Atomic Energy of Canada Ltd., Mississauga, ON (Canada)
- Ontario Hydro, Toronto, ON (Canada)
Citation Formats
Younis, M H, and Gaboury, G.
A comparison of LOCA analysis using SMOKIN and CERBERUS codes.
Canada: N. p.,
1995.
Web.
Younis, M H, & Gaboury, G.
A comparison of LOCA analysis using SMOKIN and CERBERUS codes.
Canada.
Younis, M H, and Gaboury, G.
1995.
"A comparison of LOCA analysis using SMOKIN and CERBERUS codes."
Canada.
@misc{etde_545980,
title = {A comparison of LOCA analysis using SMOKIN and CERBERUS codes}
author = {Younis, M H, and Gaboury, G}
abstractNote = {This paper presents the results of a comparison of the analyses of a postulated Loss of Coolant Accident (LOCA) in Pickering NGS A reactors using the two neutron kinetics codes SMOKIN and CERBERUS. Both codes have been used to simulate the space-time neutronic behaviour of CANDU-PHWR reactors. The main objective of the present study is to evaluate the accuracy with which SMOKIN can predict power transients compared to CERBERUS. The comparison shows that the two codes produce similar bulk power and reactivity transients. However, SMOKIN was found to overestimate the power transient (relative to CERBERUS) in some regions of the core, which is indicative of the spatial differences between the two codes. It was demonstrated that part of this overestimate is due to the use of reaction-rate averaged fuel properties in SMOKIN, compared to instantaneous fuel properties in CERBERUS. (author). 5 refs., 3 tabs., 6 figs.}
place = {Canada}
year = {1995}
month = {Dec}
}
title = {A comparison of LOCA analysis using SMOKIN and CERBERUS codes}
author = {Younis, M H, and Gaboury, G}
abstractNote = {This paper presents the results of a comparison of the analyses of a postulated Loss of Coolant Accident (LOCA) in Pickering NGS A reactors using the two neutron kinetics codes SMOKIN and CERBERUS. Both codes have been used to simulate the space-time neutronic behaviour of CANDU-PHWR reactors. The main objective of the present study is to evaluate the accuracy with which SMOKIN can predict power transients compared to CERBERUS. The comparison shows that the two codes produce similar bulk power and reactivity transients. However, SMOKIN was found to overestimate the power transient (relative to CERBERUS) in some regions of the core, which is indicative of the spatial differences between the two codes. It was demonstrated that part of this overestimate is due to the use of reaction-rate averaged fuel properties in SMOKIN, compared to instantaneous fuel properties in CERBERUS. (author). 5 refs., 3 tabs., 6 figs.}
place = {Canada}
year = {1995}
month = {Dec}
}