PELTAN, Tomáš, Eva VILÍMOVÁ, Tomáš CZAKOJ, Zdeněk MATĚJ, Filip MRAVEC, František CVACHOVEC, Jan ŠIMON, Vlastimil JUŘÍČEK and Michal KOŠŤÁL. Characterisation of neutron field in large graphite insertion in special core of the LR-0 reactor. ANNALS OF NUCLEAR ENERGY. UNITED STATES: PERGAMON-ELSEVIER SCIENCE LTD, 2023, vol. 181, No 1, p. 1-11. ISSN 0306-4549. Available from: https://dx.doi.org/10.1016/j.anucene.2022.109557.
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Basic information
Original name Characterisation of neutron field in large graphite insertion in special core of the LR-0 reactor
Authors PELTAN, Tomáš (guarantor), Eva VILÍMOVÁ, Tomáš CZAKOJ, Zdeněk MATĚJ (203 Czech Republic, belonging to the institution), Filip MRAVEC (203 Czech Republic, belonging to the institution), František CVACHOVEC (203 Czech Republic, belonging to the institution), Jan ŠIMON, Vlastimil JUŘÍČEK and Michal KOŠŤÁL.
Edition ANNALS OF NUCLEAR ENERGY, UNITED STATES, PERGAMON-ELSEVIER SCIENCE LTD, 2023, 0306-4549.
Other information
Original language English
Type of outcome Article in a journal
Field of Study 20201 Electrical and electronic engineering
Country of publisher Netherlands
Confidentiality degree is not subject to a state or trade secret
WWW URL
Impact factor Impact factor: 1.900 in 2022
RIV identification code RIV/00216224:14330/23:00133900
Organization unit Faculty of Informatics
Doi http://dx.doi.org/10.1016/j.anucene.2022.109557
UT WoS 000890345200001
Keywords in English Graphite cross-section validation; Graphite shaped neutron field; Reference neutron field; Monte Carlo Simulation
Changed by Changed by: RNDr. Pavel Šmerk, Ph.D., učo 3880. Changed: 7/4/2024 23:56.
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.
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