Abstract
The first high power and equilibrium LEU cores of PARR-1 have been analysed to assess the maximum operating power based on natural convection cooling, need for forced cooling to remove the decay heat and to estimate safety margins that commensurate with the predetermined power limit. Computer code NATCON and standard correlations have been used for the analysis. The parameters studied includes coolant velocity, temperature distribution in the core, heat fluxes at onset of nucleate boiling, pulsed boiling and burnup. (author).
Citation Formats
Khan, L A, Bokhari, I H, and Akhtar, K M.
Natural convection cooling of LEU cores for Pakistan research reactor-1.
Pakistan: N. p.,
1991.
Web.
Khan, L A, Bokhari, I H, & Akhtar, K M.
Natural convection cooling of LEU cores for Pakistan research reactor-1.
Pakistan.
Khan, L A, Bokhari, I H, and Akhtar, K M.
1991.
"Natural convection cooling of LEU cores for Pakistan research reactor-1."
Pakistan.
@misc{etde_10118286,
title = {Natural convection cooling of LEU cores for Pakistan research reactor-1}
author = {Khan, L A, Bokhari, I H, and Akhtar, K M}
abstractNote = {The first high power and equilibrium LEU cores of PARR-1 have been analysed to assess the maximum operating power based on natural convection cooling, need for forced cooling to remove the decay heat and to estimate safety margins that commensurate with the predetermined power limit. Computer code NATCON and standard correlations have been used for the analysis. The parameters studied includes coolant velocity, temperature distribution in the core, heat fluxes at onset of nucleate boiling, pulsed boiling and burnup. (author).}
place = {Pakistan}
year = {1991}
month = {Aug}
}
title = {Natural convection cooling of LEU cores for Pakistan research reactor-1}
author = {Khan, L A, Bokhari, I H, and Akhtar, K M}
abstractNote = {The first high power and equilibrium LEU cores of PARR-1 have been analysed to assess the maximum operating power based on natural convection cooling, need for forced cooling to remove the decay heat and to estimate safety margins that commensurate with the predetermined power limit. Computer code NATCON and standard correlations have been used for the analysis. The parameters studied includes coolant velocity, temperature distribution in the core, heat fluxes at onset of nucleate boiling, pulsed boiling and burnup. (author).}
place = {Pakistan}
year = {1991}
month = {Aug}
}