Abstract
In connection with upgradation of PARR-1 from 9 to 10 MW, the effects of enhanced power on various neutronic parameters have been investigated. These include: neutron energy spectrum, absolute and relative flux, control rod of worth and shutdown margin, fission product poisons, kinetic parameters, temperature coefficients of reactivity, fuel burnup and core excess reactivity. Results indicate that the reactor operation at 10 MW will improve neutron flux levels without compromising on reactor safety. (author).
Liaquat, L A
[1]
- Pakistan Inst. of Nuclear Science and Technology, Islamabad (Pakistan). Nuclear Engineering Div.
Citation Formats
Liaquat, L A.
Neutronic analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW.
Pakistan: N. p.,
1993.
Web.
Liaquat, L A.
Neutronic analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW.
Pakistan.
Liaquat, L A.
1993.
"Neutronic analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW."
Pakistan.
@misc{etde_10113676,
title = {Neutronic analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW}
author = {Liaquat, L A}
abstractNote = {In connection with upgradation of PARR-1 from 9 to 10 MW, the effects of enhanced power on various neutronic parameters have been investigated. These include: neutron energy spectrum, absolute and relative flux, control rod of worth and shutdown margin, fission product poisons, kinetic parameters, temperature coefficients of reactivity, fuel burnup and core excess reactivity. Results indicate that the reactor operation at 10 MW will improve neutron flux levels without compromising on reactor safety. (author).}
place = {Pakistan}
year = {1993}
month = {Dec}
}
title = {Neutronic analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW}
author = {Liaquat, L A}
abstractNote = {In connection with upgradation of PARR-1 from 9 to 10 MW, the effects of enhanced power on various neutronic parameters have been investigated. These include: neutron energy spectrum, absolute and relative flux, control rod of worth and shutdown margin, fission product poisons, kinetic parameters, temperature coefficients of reactivity, fuel burnup and core excess reactivity. Results indicate that the reactor operation at 10 MW will improve neutron flux levels without compromising on reactor safety. (author).}
place = {Pakistan}
year = {1993}
month = {Dec}
}