Abstract
Kinetics analysis of an aqueous homogeneous fissile solution system has been made under accidental conditions. Using the calculated values of effective delayed neutron fraction, the mean prompt neutron life time and a fission track nucleation model, computations have been made of the power and integrated energy release for step reactivity insertions and the results compared with French experiments. Analysis of the dynamics of power excursions obtained in kinetic experiments shows that there is a simple relation for estimating the total fission yield in homogeneous solution of fissile material when it is subjected to power transients. (author). 13 refs., 6 figs.
Das, S
[1]
- Bhabha Atomic Research Centre, Bombay (India). Theoretical Physics Div.
Citation Formats
Das, S.
Criticality accident in homogeneous solution of fissile material.
India: N. p.,
1992.
Web.
Das, S.
Criticality accident in homogeneous solution of fissile material.
India.
Das, S.
1992.
"Criticality accident in homogeneous solution of fissile material."
India.
@misc{etde_10129552,
title = {Criticality accident in homogeneous solution of fissile material}
author = {Das, S}
abstractNote = {Kinetics analysis of an aqueous homogeneous fissile solution system has been made under accidental conditions. Using the calculated values of effective delayed neutron fraction, the mean prompt neutron life time and a fission track nucleation model, computations have been made of the power and integrated energy release for step reactivity insertions and the results compared with French experiments. Analysis of the dynamics of power excursions obtained in kinetic experiments shows that there is a simple relation for estimating the total fission yield in homogeneous solution of fissile material when it is subjected to power transients. (author). 13 refs., 6 figs.}
place = {India}
year = {1992}
month = {Dec}
}
title = {Criticality accident in homogeneous solution of fissile material}
author = {Das, S}
abstractNote = {Kinetics analysis of an aqueous homogeneous fissile solution system has been made under accidental conditions. Using the calculated values of effective delayed neutron fraction, the mean prompt neutron life time and a fission track nucleation model, computations have been made of the power and integrated energy release for step reactivity insertions and the results compared with French experiments. Analysis of the dynamics of power excursions obtained in kinetic experiments shows that there is a simple relation for estimating the total fission yield in homogeneous solution of fissile material when it is subjected to power transients. (author). 13 refs., 6 figs.}
place = {India}
year = {1992}
month = {Dec}
}