A program on fast reactor safety is described in which the theoretical aspects, techniques and accuracy of calculation, and associated safety predictions are considered. One topic deals with the success obtained in analyzing complicated meltdown configurations using two-dimensional, twogroup diffusion theory. Another topic deals with the dependence of energy yield in a fast reactor explosion on the shape of the power distribution in the core. The results of a brief survey are included dealing with the change of dynamic reactor behavior during various startup accidents as a consequence of a reduction in the delayed-neutron fraction. (J.R.D.
The FAST code system is a general tool for analyzing advanced reactors from the viewpoint of the sta...
Results are summarized for a survey of methods for predicting fuel element and coolant behavior in s...
This paper characterizes the areas of Integral Fast Reactor (IFR) safety research in terms of their ...
Multigroup diffusion theory calculations performed in connection with the fast power breeder reactor...
The dynamic behavior of a fast reactor, when the neutron flux is considered as a function of time, i...
The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, lic...
Accurate modeling of different phenomena ( e.g. fluid-dynamics, neutronics...) is fundamental in pre...
A postulated fast reactor accident which has been extant for many years is a recriticality following...
Sodium-cooled fast reactors are designed to have a high level of safety. Events of high probability ...
The methods applied or proposed for risk assessment of nuclear reactors are reviewed, particularly w...
The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, lic...
ISBN : 9781510872622International audienceWithin the framework of the Generation IV Sodium-cooled Fa...
The sensitivity of the reactivity of a fast reactor core to changes in its geometry and/or fuel relo...
A vast amount of research and development work has been done in recent years to resolve the issues o...
A fast reactor may be defined as a reactor in which the neutron energy distribution differs as littl...
The FAST code system is a general tool for analyzing advanced reactors from the viewpoint of the sta...
Results are summarized for a survey of methods for predicting fuel element and coolant behavior in s...
This paper characterizes the areas of Integral Fast Reactor (IFR) safety research in terms of their ...
Multigroup diffusion theory calculations performed in connection with the fast power breeder reactor...
The dynamic behavior of a fast reactor, when the neutron flux is considered as a function of time, i...
The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, lic...
Accurate modeling of different phenomena ( e.g. fluid-dynamics, neutronics...) is fundamental in pre...
A postulated fast reactor accident which has been extant for many years is a recriticality following...
Sodium-cooled fast reactors are designed to have a high level of safety. Events of high probability ...
The methods applied or proposed for risk assessment of nuclear reactors are reviewed, particularly w...
The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, lic...
ISBN : 9781510872622International audienceWithin the framework of the Generation IV Sodium-cooled Fa...
The sensitivity of the reactivity of a fast reactor core to changes in its geometry and/or fuel relo...
A vast amount of research and development work has been done in recent years to resolve the issues o...
A fast reactor may be defined as a reactor in which the neutron energy distribution differs as littl...
The FAST code system is a general tool for analyzing advanced reactors from the viewpoint of the sta...
Results are summarized for a survey of methods for predicting fuel element and coolant behavior in s...
This paper characterizes the areas of Integral Fast Reactor (IFR) safety research in terms of their ...