Abstract
One of the ways of enhancing the passive safety of a CANDU-PHW (Canada Deuterium Uranium-Pressurized heavy Water) reactor is to reduce the moderator subcooling requirements during a postulated loss-of-coolant accident (LOCA). The increased moderator temperatures would enhance the heat transfer from the moderator to the surrounding shield tank during a postulated accident. This reduction in subcooling requirements can be achieved by incorporating a wire screen in the fuel-channel annulus, right next to the calandria tube. This technique has been demonstrated to reduce significantly the moderator subcooling requirements, so that the calandria tube was not forced into film boiling upon pressure-tube ballooning contact with 0 degrees C subcooling outside the calandria tube. Two experiments, described in this report, were performed at AECL Research`s Whiteshell Laboratories to investigate the changes in heat transfer characteristics between a pressure tube and a calandria tube, with a wire screen placed in the fuel-channel annulus. Results from computer simulations performed to assess the effect of the wire screen on the performance of a CANDU fuel channel during selected LOCA scenarios are also presented.
Citation Formats
Sanderson, D B, Moyer, R G, Litke, D G, Rosinger, H E, and Girgis, S.
Reduction of pressure-tube to calandria-tube contact conductance to enhance the passive safety of a CANDU-PHW reactor.
Canada: N. p.,
1993.
Web.
Sanderson, D B, Moyer, R G, Litke, D G, Rosinger, H E, & Girgis, S.
Reduction of pressure-tube to calandria-tube contact conductance to enhance the passive safety of a CANDU-PHW reactor.
Canada.
Sanderson, D B, Moyer, R G, Litke, D G, Rosinger, H E, and Girgis, S.
1993.
"Reduction of pressure-tube to calandria-tube contact conductance to enhance the passive safety of a CANDU-PHW reactor."
Canada.
@misc{etde_10138445,
title = {Reduction of pressure-tube to calandria-tube contact conductance to enhance the passive safety of a CANDU-PHW reactor}
author = {Sanderson, D B, Moyer, R G, Litke, D G, Rosinger, H E, and Girgis, S}
abstractNote = {One of the ways of enhancing the passive safety of a CANDU-PHW (Canada Deuterium Uranium-Pressurized heavy Water) reactor is to reduce the moderator subcooling requirements during a postulated loss-of-coolant accident (LOCA). The increased moderator temperatures would enhance the heat transfer from the moderator to the surrounding shield tank during a postulated accident. This reduction in subcooling requirements can be achieved by incorporating a wire screen in the fuel-channel annulus, right next to the calandria tube. This technique has been demonstrated to reduce significantly the moderator subcooling requirements, so that the calandria tube was not forced into film boiling upon pressure-tube ballooning contact with 0 degrees C subcooling outside the calandria tube. Two experiments, described in this report, were performed at AECL Research`s Whiteshell Laboratories to investigate the changes in heat transfer characteristics between a pressure tube and a calandria tube, with a wire screen placed in the fuel-channel annulus. Results from computer simulations performed to assess the effect of the wire screen on the performance of a CANDU fuel channel during selected LOCA scenarios are also presented.}
place = {Canada}
year = {1993}
month = {Nov}
}
title = {Reduction of pressure-tube to calandria-tube contact conductance to enhance the passive safety of a CANDU-PHW reactor}
author = {Sanderson, D B, Moyer, R G, Litke, D G, Rosinger, H E, and Girgis, S}
abstractNote = {One of the ways of enhancing the passive safety of a CANDU-PHW (Canada Deuterium Uranium-Pressurized heavy Water) reactor is to reduce the moderator subcooling requirements during a postulated loss-of-coolant accident (LOCA). The increased moderator temperatures would enhance the heat transfer from the moderator to the surrounding shield tank during a postulated accident. This reduction in subcooling requirements can be achieved by incorporating a wire screen in the fuel-channel annulus, right next to the calandria tube. This technique has been demonstrated to reduce significantly the moderator subcooling requirements, so that the calandria tube was not forced into film boiling upon pressure-tube ballooning contact with 0 degrees C subcooling outside the calandria tube. Two experiments, described in this report, were performed at AECL Research`s Whiteshell Laboratories to investigate the changes in heat transfer characteristics between a pressure tube and a calandria tube, with a wire screen placed in the fuel-channel annulus. Results from computer simulations performed to assess the effect of the wire screen on the performance of a CANDU fuel channel during selected LOCA scenarios are also presented.}
place = {Canada}
year = {1993}
month = {Nov}
}