Experimental validation of VESTA 2.1

Author:

Haeck W.,Cochet B.,Bernard F.,Tymen A.

Abstract

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.

Publisher

EDP Sciences

Reference17 articles.

1. Haeck W., “VESTA User’s Manual - Version 2.0.0”, IRSN Report DSU/SEC/T/2008-331 Index A, Institut de Radioprotection et de Sûreté Nucléaire, France (2009)

2. Haeck W., “VESTA User’s Manual - Version 2.1.0”, IRSN Report DSU/SEC/T/2012-081 Index A, Institut de Radioprotection et de Sûreté Nucléaire, France (2012)

3. Haeck W., Cochet B., Aguiar L., “Monte Carlo Depletion Calculations Using VESTA 2.1”, PHYSOR 2012, Knoxville, USA, 2012

4. Hendricks J. S. et al., “MCNPX, VERSION 2.6.a”, LA-UR-05-8225, Los Alamos National Laboratory, USA (2005)

5. Croff A. G., “ORIGEN2 - A Revised and Updated Version of the Oak Ridge Isotope Generation and Depletion Code”, ORNL- 5621, Oak Ridge National Laboratory, USA (1980)

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