In this work, a study dedicated to the characterization of the neutronics aspect of the Spent Nuclear Fuel (SNF), as part of the European project EURAD (Work Package 8), is presented. Both measured nuclide concentrations from Post Irradiation Examination samples and decay heat from calorimetric measurements are compared to simulations performed by different partners of the project. Based on these detailed studies and data from the published literature, recommendations are proposed with respect to best practices for SNF modelling, as well as biases and uncertainties for a number of important nuclides and the SNF decay heat for a cooling period from 1 to 1000 years. Finally, specific needs are presented for the improvement of current code pre...
Oak Ridge National Laboratory (ORNL) has a long history of involvement in the development and valida...
Decay heat calculations of spent nuclear fuel (SNF) using Polaris and ORIGEN codes in the SCALE code...
Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and mea...
In this work, a study dedicated to the characterization of the neutronics aspect of the Spent Nuclea...
In this work, a study dedicated to the characterization of the neutronics aspect of the Spent Nuclea...
Studsvik’s approach to spent nuclear fuel analyses combines isotopic concentrations and multi-group ...
Studsvik’s approach to spent nuclear fuel analyses combines isotopic concentrations, fluxes, and cro...
Accurate nuclear data are essential in the evaluation of decay heat from spent nuclear fuel (SNF). T...
In this paper, we validate the decay heat calculation capability via a two-step method to analyze sp...
The objective of this calculation is to determine decay heat of a pressurized-water reactor (PWR) sp...
This paper presents a study of the impact of the nuclear data (cross sections, neutron emission and ...
The amount of Spent Nuclear Fuel (SNF) generated in the world is increasing over time. Moreover, it ...
Knowledge of spent nuclear fuel (SNF) source term, for example decay heat, reactivity and nuclide in...
Knowledge of spent nuclear fuel (SNF) source term (decay heat, reactivity, nuclide inventory and oth...
Characteristics of the spent nuclear fuel (SNF) are typically calculated, requiring validation a pri...
Oak Ridge National Laboratory (ORNL) has a long history of involvement in the development and valida...
Decay heat calculations of spent nuclear fuel (SNF) using Polaris and ORIGEN codes in the SCALE code...
Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and mea...
In this work, a study dedicated to the characterization of the neutronics aspect of the Spent Nuclea...
In this work, a study dedicated to the characterization of the neutronics aspect of the Spent Nuclea...
Studsvik’s approach to spent nuclear fuel analyses combines isotopic concentrations and multi-group ...
Studsvik’s approach to spent nuclear fuel analyses combines isotopic concentrations, fluxes, and cro...
Accurate nuclear data are essential in the evaluation of decay heat from spent nuclear fuel (SNF). T...
In this paper, we validate the decay heat calculation capability via a two-step method to analyze sp...
The objective of this calculation is to determine decay heat of a pressurized-water reactor (PWR) sp...
This paper presents a study of the impact of the nuclear data (cross sections, neutron emission and ...
The amount of Spent Nuclear Fuel (SNF) generated in the world is increasing over time. Moreover, it ...
Knowledge of spent nuclear fuel (SNF) source term, for example decay heat, reactivity and nuclide in...
Knowledge of spent nuclear fuel (SNF) source term (decay heat, reactivity, nuclide inventory and oth...
Characteristics of the spent nuclear fuel (SNF) are typically calculated, requiring validation a pri...
Oak Ridge National Laboratory (ORNL) has a long history of involvement in the development and valida...
Decay heat calculations of spent nuclear fuel (SNF) using Polaris and ORIGEN codes in the SCALE code...
Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and mea...