| Issue |
2014
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
|
|
|---|---|---|
| Article Number | 03603 | |
| Number of page(s) | 15 | |
| Section | 3. Monte Carlo Methods for Simulation: f. New Monte Carlo Applications and Benchmarking | |
| DOI | https://doi.org/10.1051/snamc/201403603 | |
| Published online | 06 June 2014 | |
Experimental validation of VESTA 2.1
1 Institut de Radioprotection et de Sûreté Nucléaire (IRSN), BP 17, 92262 Fontenay-aux-Roses, France
2 External consultant
Depletion codes such as VESTA are used to calculate the evolution of a material subjected to radiation (be it neutrons or another type of particle) for a wide variety of applications in the fields of nuclear safety, radiation protection and environmental health safety. For these applications, experimental validation is paramount. In this paper we will describe the experimental validation of the latest version of VESTA using a set of 76 samples consisting of radiochemical assay data and decay heat measurements. We will describe the general calculation procedure that has been applied to determine the uncertainty on each individual nuclide measurement as well as the general tendencies and detailed results.
Key words: depletion calculations / experimental validation / VESTA
© Owned by the authors, published by EDP Sciences, 2014