Abstract
Uncertainties in the kinetic response of a 500 MWe Prototype Fast Breeder Reactor design to large changes in delayed-neutron energies have been calculated using point kinetics method and the concepts of Delayed Spectrum Factor and Beta Growth Factor. Positive reactivity accidents are postulated. Calculations show that delayed-neutron spectra have little influence on the shapes of the transients, though the spread is within about 27% for the peak power attained and about 20% for the accident energy released. However, the relative power level shows a much greater sensitivity. (author). 5 refs., 3 tabs.
Das, S
[1]
- Bhabha Atomic Research Centre, Bombay (India). Theoretical Physics Div.
Citation Formats
Das, S.
Uncertainty in the dynamic behaviour of a fast breeder reactor to delayed-neutron energy spectra.
India: N. p.,
1993.
Web.
Das, S.
Uncertainty in the dynamic behaviour of a fast breeder reactor to delayed-neutron energy spectra.
India.
Das, S.
1993.
"Uncertainty in the dynamic behaviour of a fast breeder reactor to delayed-neutron energy spectra."
India.
@misc{etde_10127206,
title = {Uncertainty in the dynamic behaviour of a fast breeder reactor to delayed-neutron energy spectra}
author = {Das, S}
abstractNote = {Uncertainties in the kinetic response of a 500 MWe Prototype Fast Breeder Reactor design to large changes in delayed-neutron energies have been calculated using point kinetics method and the concepts of Delayed Spectrum Factor and Beta Growth Factor. Positive reactivity accidents are postulated. Calculations show that delayed-neutron spectra have little influence on the shapes of the transients, though the spread is within about 27% for the peak power attained and about 20% for the accident energy released. However, the relative power level shows a much greater sensitivity. (author). 5 refs., 3 tabs.}
place = {India}
year = {1993}
month = {Dec}
}
title = {Uncertainty in the dynamic behaviour of a fast breeder reactor to delayed-neutron energy spectra}
author = {Das, S}
abstractNote = {Uncertainties in the kinetic response of a 500 MWe Prototype Fast Breeder Reactor design to large changes in delayed-neutron energies have been calculated using point kinetics method and the concepts of Delayed Spectrum Factor and Beta Growth Factor. Positive reactivity accidents are postulated. Calculations show that delayed-neutron spectra have little influence on the shapes of the transients, though the spread is within about 27% for the peak power attained and about 20% for the accident energy released. However, the relative power level shows a much greater sensitivity. (author). 5 refs., 3 tabs.}
place = {India}
year = {1993}
month = {Dec}
}