Investigating the breeding capabilities of hybrid soliton reactors

• Published in: Nuclear engineering and design 2013-08, Vol.261, p.251-259
• Main Authors: Catsaros, N., Gaveau, B., Jaekel, M.-T., Jejcic, A., Maillard, J., Maurel, G., Savva, P., Silva, J., Varvayanni, M., Xenofontos, T.
• Format: Article
• Language: English
• Subjects: Accelerators; Computer simulation; General Relativity and Quantum Cosmology; Nuclear engineering; Nuclear power generation; Nuclear reactor components; Nuclear reactors; Nuclear Theory; Physics; Pressurized water reactors; Solitons
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/j.nucengdes.2013.04.022

•ANET code simulates innovative reactor designs including Accelerator Driven Systems.•Preliminary analysis of thermal hybrid soliton reactor examines breeding capabilities.•Subsequent studies will aim at optimizing parameters examined in this analysis.•Breeding capacity could be obtained while preserving efficiency and reactor stability. Nuclear energy industry asks for an optimized exploitation of available natural resources and a safe operation of reactors. A closed fuel cycle requires the mass of fissile material depleted in a reactor to be equal to or less than the fissile mass produced in the same or in other reactors. In this work, a simple closed cycle scheme is investigated, grounded on the use of a conceptual thermal water-cooled and moderated subcritical hybrid soliton reactor (HSR). The concept is a specific Accelerator Driven System (ADS) operating at lower power than usual pressurized water reactors (PWRs). This type of reactor can be inherently safe, since shutdown is achieved by simply interrupting the accelerator's power supply. In this work a preliminary investigation is attempted concerning the existence of conditions under which the operation of a thermal HSR in breeding regime is possible. For this purpose, a conceptual encapsulated core has been defined by choosing the magnitude of a set of parameters which are important from the neutronic point of view, such as core geometry and fuel composition. Indications of breeding operation regime for thermal HSR systems are sought by performing preliminary simulations of this core. For this purpose, the Monte Carlo code ANET, which is being developed based on the high energy physics code GEANT is utilized, as being capable of simulating particles’ transport and interactions produced, including also simulation of low energy neutrons transport. A simple analytical model is also developed and presented in order to investigate the conditions under which breeding in HSR is possible, which supports the ANET simulation findings.