Neutronic comparison of liquid breeders for ARC-like reactor blankets

The proposed blanket for Affordable Robust Compact (ARC) reactor is one of the simplest blanket concepts. It is a bulk tank filled with a lithium and beryllium fluorides molten salt. The fluid effectively works as tritium breeder, vessel coolant and neutron moderator and shield. However, despite the simplicity of the concept, the compactness of the reactor constitutes a novelty in the fusion field. It is thus necessary to evaluate all the possible solutions for an effective blanket component. This work analyses different liquid blanket identifying the most suitable for a compact fusion reactor. More specifically, the study addresses the capability of breeding tritium in a compact solution, actively shielding the coils and reducing the radioactive waste. Findings are that FLiBe optimizes the most the system in terms of applicability, tritium breeding, compactness and activation. Nonetheless, there is no lack of backup choices. For instance, there are hints that lithium-zirconium fluoride salts could accomplish the blanket main tasks in a compact reactor too. Leaving PbLi as inefficient, but cheap and still virtually viable solution

OpenMC data for simulating ARC reactor blanket

The following datasets are the main OpenMC output files converted from dataframe to xlsx files. They are divided in the enrichment folder, where each salt has been parametrized over Li-6 enrichment fraction, and the mesh folder, where mesh results have been used for coming up with the cumulative curves over distance from the neutron source. Each folder contains a Python input as example of the model used

OpenMC data for simulating ARC reactor blanket

The following datasets are the main OpenMC output files converted from dataframe to xlsx files. They are divided in the enrichment folder, where each salt has been parametrized over Li-6 enrichment fraction, and the mesh folder, where mesh results have been used for coming up with the cumulative curves over distance from the neutron source. Each folder contains a Python input as example of the model used

ARC reactor – Neutron irradiation analysis

Neutron irradiation is one of the most concerning issues to design plasma facing components and reactor inner structures in fusion devices, especially for high power density ones, like ARC reactor. This study addresses the main aspects of neutron irradiation on solid materials of ARC reactor. In particular it deeply analizes the effect of neutron induced activation proposing low activation structures, like vanadium alloys and different optimization methods like isotopic tailoring, detritiation and impurity control. Furthermore, irradiation damage issues and their dependence on the energy spectrum are highlighted. It resulted that V-Cr-Ti alloys dramatically reduce the radioactive inventory of ARC with respect to its baseline configuration, which proposes the application of Inconel 718. Such alloy is also optimizable through the tailoring of titanium isotopes and is virtually capable of hitting recycle limits in a couple of decades. Lastly, it shows a relatively growth of gas during irradiation. However, it is highlighted how experiments on neutron damage featuring fission neutrons risk to be able to tell very little about the behavior of the same materials under fusion neutrons, as damaging mechanisms seem to be different

Data for: Exploration of power conversion thermodynamic cycles for ARC fusion reactor

Example of Python script developed for the optimization of the thermodynamic efficiency of a possible thermodynamic cycle applied to ARC reactor.THIS DATASET IS ARCHIVED AT DANS/EASY, BUT NOT ACCESSIBLE HERE. TO VIEW A LIST OF FILES AND ACCESS THE FILES IN THIS DATASET CLICK ON THE DOI-LINK ABOV

Most advanced technological innovation as a part of simple solutions for the world energy problem

Energy studies are today interdisciplinary studies. They involve not just technical aspects, but also environmental, social and politic aspects. In this framework, an interdisciplinary approach to help solve energy issue through advanced technological innovations as a part of simple solution for the energy problem is considered. Two case studies were reported: the role of the fusion energy as new energy source and the methods to degrade polychlorinated biphenyls, synthetic compounds used in energy field, to reduce its environmental impact

FUSION ENERGY AND THE ARC PROJECT

The recent progress in fields such as High Temperature Superconductors (HTS), Additive manufacturing, new diagnostics, and innovative materials, has led to new scenarios and to a second generation of Nuclear Fusion Reactor designs. The new Affordable Robust Compact (ARC) Fusion Reactor is described in the paper. ARC could be not only the base-load but also a load-following reactor, capable to cover peak requests and other plant shutdowns. In order to investigate this interesting ability of ARC, its more sensitive component has been analyzed: ARC vacuum vessel

Review of nuclear microreactors: Status, potentialities and challenges

Nuclear energy is being reconsidered worldwide as a low-carbon and dispatchable energy source. Following the development of Small Modular Reactors (SMR) to reduce the capital costs and increase the safety of new nuclear power plants, microreactors are being designed by several companies. Microreactors are usually defined as SMR with a power output in the range 1–20 MWe. They can operate as part of the electric grid, independently from the electric grid or as part of a microgrid to produce electricity and process heat. In the present paper, some microreactors at an advanced design stage are presented: eVinci™, Aurora, Holos Generators, Xe-Mobile, NuScale, Sealer, U-Battery and Micro Modular Reactor. The main applications of microreactors and the technology features are then discussed to present the main potentialities and challenges. The main advantages are the small size, the simple plant layout and the fast on-site installation. The main challenges are the limited fuel availability, the security and proliferation risk and the licensing process. Finally, an economic analysis shows that, due to an economy of scale, despite the capital cost reduction, microreactors are not cost competitive with large nuclear plants, but they are competitive with technologies with similar scale and application, such as diesel generators and renewable sources in microgrids

Preliminary investigation of neutron shielding compounds for ARC-class tokamaks

Radiation shielding design is a crucial step in the development of a nuclear fusion reactor. Superconducting magnets are indeed a highly engineered component whose properties are particularly sensitive to irradiation damage. In addition, novel magnet technologies, such as High Temperature Superconductors (HTS), and the attractiveness of compact tokamak designs (like Affordable Robust Compact - ARC - reactor), require an even higher precision in the shielding design. In this work most promising radiation shielding solutions for compact tokamaks are explored. The study applies a Monte Carlo particles transport technique assisted by the OpenMC code. A D-shaped model is built and ARC reactor core is considered as main case study. A detailed analysis of the radiation environment is carried out. The study then assesses the most promising compounds on the basis of most suitable cross sections, material shielding properties and space constraints. In addition, the work addresses the problem of energy deposition on the shield providing an analytical model for active cooling necessities. Results highlighted the necessity of heavy elements and high density compounds as a considerable photon flux is generated in neutron-material interactions. Tungsten borides (WxBy) ceramics seem to be particularly promising for shielding radiation in a compact configuration