Characterisation of neutron field in large graphite insertion in special core of the LR-0 reactor. (February 2023)

• Record Type: Journal Article
• Authors: Peltan, Tomáš; Vilímová, Eva; Czakoj, Tomáš; Matěj, Zdeněk; Mravec, Filip; Cvachovec, František; Šimon, Jan; Juříček, Vlastimil; Košťál, Michal
• Is Part Of: Annals of nuclear energy. Volume 181(2023)
• Publication Date: 2023-02
• Subjects: Graphite cross-section validation -- Graphite shaped neutron field -- Reference neutron field -- Monte Carlo Simulation; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2022.109557
• Languages: English
• ISSNs: 0306-4549

Abstract

Abstract: Graphite is important reactor material used as a neutron moderator in various reactor designs. It is not only structural material used in previous reactors design but even material to which attention is focused due to the very high-temperature reactor design, which uses graphite as moderator and reflector. Due to the well-characterised cross-section of graphite, it is also a good candidate for neutron shaping experiments. In this kind of experiment, the neutron spectra are modified to the unconventional shape of neutron spectra which can be used to validate cross-section. This paper deals with validation of neutron field in graphite block surrounded by driver core arranged in large special core in LR-0 reactor. The experimentally determined shape of neutron spectra and spatial distribution of neutron flux is compared with the calculation. It is worth noting that the agreement for flux distribution is satisfactory in regions below the moderator level.