ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Apr 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
May 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
India’s PFBR attains criticality at last
Prime Minister Narendra Modi proclaimed it “a proud moment for India” when on April 6 the 500-MWe, sodium-cooled Prototype Fast Breeder Reactor (PFBR) achieved initial criticality. This milestone, which comes some 22 years after the continually delayed PFBR project began, marks India’s entrance into the second stage of its three-stage nuclear program, which has the ultimate goal of supporting the country’s nuclear power program with its significant thorium reserves.
Benjamin Dechenaux
Nuclear Science and Engineering | Volume 195 | Number 5 | May 2021 | Pages 538-554
Technical Paper | doi.org/10.1080/00295639.2020.1847980
Articles are hosted by Taylor and Francis Online.
The analysis of the results of a depletion code is often considered a tedious and delicate task, for it requires both the processing of large volumes of information (the time-dependent composition of up to thousands of isotopes) and an extensive knowledge of nuclear reactions and associated nuclear data. From these observations, dedicated developments have been integrated to the upcoming version of the Monte Carlo depletion code VESTA 2.2 in order to implement an innovative representation of depletion problems. The aim is to provide users with an adaptable and efficient framework to ease the analysis of the results of the code and facilitate their interpretation. This effort ultimately culminates in the development of the representation of the isotopic evolution of a given system as a directed graph.
In this paper, it is shown that the Bateman equation encoded in the VESTA code indeed possesses a natural interpretation in terms of a directed cyclic graph, and it is proposed to explore some of the insight one can gain from the graph representation of a depletion problem. Starting from the new capabilities of the code, it is shown how one can build on the wealth of existing methods of graph theory in order to gain useful information about the nuclear reactions taking place in a material under irradiation. The graph representation of a depletion problem being especially simple in activation problems—for then only a limited number of nuclides and reactions are involved—the graph representation and its associated tools will be used to study the evolution of the structure materials of a simplified model of the ITER fusion reactor.