an analysis of selected fission fragment angular distributions from helium-ion induced fission is made using an exact theoretical expression. theoretical anisotropies obtained with the transition state model are compared with their corresponding values deduced from the statistical scission model. the nuclear moment of inertia extracted from the model calculations are compared with their estimat...

An analysis of selected fission fragment angular distributions from helium-ion induced fission is made using an exact theoretical expression. Theoretical anisotropies obtained with the transition state model are compared with their corresponding values deduced from the statistical scission model. The nuclear moment of inertia extracted from the model calculations are compared with their est...

Criticality safety analysis is required at various stages of the back-end fuel cycle, i.e. reprocessing, transport, storage and disposal spent nuclear (SNF). To account for reduction in reactivity due to burnup, Burn-Up Credit (BUC) concept was introduced. Evidently, this depends on quality data, particular absorption cross sections some key nuclides. A dedicated programme has been established ...

A model based on the macroscopic-microscopic approach for calculating the fission-fragment properties is presented. Using this model, a large set of experimental data measured in lowand high-energy fission can be reproduced using one and same set of model parameters.

Spent fuel transportation and storage cask designs based on a burnup credit approach must consider issues that are not relevant in casks designed under a fresh-fuel loading assumption. For example, the spent fuel composition must be adequately characterized and the criticality analysis model can be complicated by the need to consider axial burnup variations. Parametric analyses are needed to ch...

The OECD Nuclear Energy Agency (NEA) started working on criticality-safety related subjects in the seventies. In the mid-nineties, several activities related to criticality-safety were grouped together into the Working Party on Nuclear Criticality Safety. This working party has since been operating and reporting to the Nuclear Science Committee. Four expert groups co-ordinate various activities...

Advanced modelling of neutron induced reactions on 238U nucleus is aimed at improving our knowledge of the neutron scattering. Capture and fission channels are well constrained by available experimental data and neutron standard evaluation. A focus of this contribution is on elastic and inelastic scattering cross sections. The employed nuclear reaction model includes – a new rotational-vibratio...