Accurate nuclear data are essential in the evaluation of decay heat from spent nuclear fuel (SNF). The accuracy of such data was assessed using an approach that compares values reported in different evaluated libraries and determines whether discrepancies reflect inaccuracies in primary data. A short list of 43 isotopes which are most significant to SNF decay heat calculations over 1–100 k years was produced by combining generic reactor inventory code with decay heat analysis for undifferentiated SNF. Decay properties (half-lives and decay energies) and neutron interactions (cross section and fission yields) were compared from 6 evaluated libraries. Fission product (FP) discrepancies identified are 90Sr half-life, where inclusion of a singl...
Knowledge of spent nuclear fuel (SNF) source term, for example decay heat, reactivity and nuclide in...
Radioactivity and decay power of spent MOX fuel are very crucial in term of storage or disposal. In ...
Oak Ridge National Laboratory (ORNL) has a long history of involvement in the development and valida...
In this paper, we validate the decay heat calculation capability via a two-step method to analyze sp...
Studsvik’s approach to spent nuclear fuel analyses combines isotopic concentrations and multi-group ...
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...
Accurate nuclear data, commonly using evaluated libraries, is essential in many applications, allowi...
Characteristics of the spent nuclear fuel (SNF) are typically calculated, requiring validation a pri...
To store the data obtained from JANIS 4.1, ENSDF and DDEP nuclear data for Tables 1 – 8, 10 – 12 fro...
The objective of this calculation is to determine decay heat of a pressurized-water reactor (PWR) sp...
Knowledge of spent nuclear fuel (SNF) source term (decay heat, reactivity, nuclide inventory and oth...
Decay heat calculations of spent nuclear fuel (SNF) using Polaris and ORIGEN codes in the SCALE code...
Computational modelling for spent nuclear fuel (SNF) characterization is already widely used and con...
Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and mea...
Knowledge of spent nuclear fuel (SNF) source term, for example decay heat, reactivity and nuclide in...
Radioactivity and decay power of spent MOX fuel are very crucial in term of storage or disposal. In ...
Oak Ridge National Laboratory (ORNL) has a long history of involvement in the development and valida...
In this paper, we validate the decay heat calculation capability via a two-step method to analyze sp...
Studsvik’s approach to spent nuclear fuel analyses combines isotopic concentrations and multi-group ...
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...
Accurate nuclear data, commonly using evaluated libraries, is essential in many applications, allowi...
Characteristics of the spent nuclear fuel (SNF) are typically calculated, requiring validation a pri...
To store the data obtained from JANIS 4.1, ENSDF and DDEP nuclear data for Tables 1 – 8, 10 – 12 fro...
The objective of this calculation is to determine decay heat of a pressurized-water reactor (PWR) sp...
Knowledge of spent nuclear fuel (SNF) source term (decay heat, reactivity, nuclide inventory and oth...
Decay heat calculations of spent nuclear fuel (SNF) using Polaris and ORIGEN codes in the SCALE code...
Computational modelling for spent nuclear fuel (SNF) characterization is already widely used and con...
Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and mea...
Knowledge of spent nuclear fuel (SNF) source term, for example decay heat, reactivity and nuclide in...
Radioactivity and decay power of spent MOX fuel are very crucial in term of storage or disposal. In ...
Oak Ridge National Laboratory (ORNL) has a long history of involvement in the development and valida...