Abstract
This paper describes the collapse load calculations for the reactor structure assembly under the postulated fuel channel flow blockage Level D (faulted) loading condition. Under the flow blockage condition, the primary coolant flow path is obstructed between the inlet and outlet feeder connections to the headers. This, in turn, is postulated to cause the pressure tube and calandria tube to rupture and release hot molten fuel into the moderator, producing a hydrodynamic transient within the calandria shell. The most severe hydrodynamic loads occur within a fraction of a second (0.14 second). The peak pressure for the limiting case scenario for Level D condition is 120 psig, due to a single channel failure event. Under this accident condition, it is shown that the reactor structure assembly can withstand the pressure transient and the structural integrity of the core is assured. A finite element model is generated and used to calculate the minimum collapse load. The ANSYS code is used with element type Stif-43 for elastic/plastic, large deformation and small strain analysis. (author). 1 ref., 3 tabs., 9 figs.
Soliman, S A;
Lee, T;
Ibrahim, A M;
Hodgson, S
[1]
- Atomic Energy of Canada Ltd., Saskatoon, SK (Canada)
Citation Formats
Soliman, S A, Lee, T, Ibrahim, A M, and Hodgson, S.
Stress analysis for CANDU reactor structure assembly following a postulated p/t, c/t rupture after flow blockage.
Canada: N. p.,
1995.
Web.
Soliman, S A, Lee, T, Ibrahim, A M, & Hodgson, S.
Stress analysis for CANDU reactor structure assembly following a postulated p/t, c/t rupture after flow blockage.
Canada.
Soliman, S A, Lee, T, Ibrahim, A M, and Hodgson, S.
1995.
"Stress analysis for CANDU reactor structure assembly following a postulated p/t, c/t rupture after flow blockage."
Canada.
@misc{etde_546000,
title = {Stress analysis for CANDU reactor structure assembly following a postulated p/t, c/t rupture after flow blockage}
author = {Soliman, S A, Lee, T, Ibrahim, A M, and Hodgson, S}
abstractNote = {This paper describes the collapse load calculations for the reactor structure assembly under the postulated fuel channel flow blockage Level D (faulted) loading condition. Under the flow blockage condition, the primary coolant flow path is obstructed between the inlet and outlet feeder connections to the headers. This, in turn, is postulated to cause the pressure tube and calandria tube to rupture and release hot molten fuel into the moderator, producing a hydrodynamic transient within the calandria shell. The most severe hydrodynamic loads occur within a fraction of a second (0.14 second). The peak pressure for the limiting case scenario for Level D condition is 120 psig, due to a single channel failure event. Under this accident condition, it is shown that the reactor structure assembly can withstand the pressure transient and the structural integrity of the core is assured. A finite element model is generated and used to calculate the minimum collapse load. The ANSYS code is used with element type Stif-43 for elastic/plastic, large deformation and small strain analysis. (author). 1 ref., 3 tabs., 9 figs.}
place = {Canada}
year = {1995}
month = {Dec}
}
title = {Stress analysis for CANDU reactor structure assembly following a postulated p/t, c/t rupture after flow blockage}
author = {Soliman, S A, Lee, T, Ibrahim, A M, and Hodgson, S}
abstractNote = {This paper describes the collapse load calculations for the reactor structure assembly under the postulated fuel channel flow blockage Level D (faulted) loading condition. Under the flow blockage condition, the primary coolant flow path is obstructed between the inlet and outlet feeder connections to the headers. This, in turn, is postulated to cause the pressure tube and calandria tube to rupture and release hot molten fuel into the moderator, producing a hydrodynamic transient within the calandria shell. The most severe hydrodynamic loads occur within a fraction of a second (0.14 second). The peak pressure for the limiting case scenario for Level D condition is 120 psig, due to a single channel failure event. Under this accident condition, it is shown that the reactor structure assembly can withstand the pressure transient and the structural integrity of the core is assured. A finite element model is generated and used to calculate the minimum collapse load. The ANSYS code is used with element type Stif-43 for elastic/plastic, large deformation and small strain analysis. (author). 1 ref., 3 tabs., 9 figs.}
place = {Canada}
year = {1995}
month = {Dec}
}