Detailed Information on Publication Record
2023
Specially developed LR-0 reactor graphite environment for gen IV reactor support and cross-section measurement
PELTAN, Tomáš, Eva VILIMOVÁ, Tomáš CZAKOJ, Zdeněk MATĚJ, Filip MRAVEC et. al.Basic information
Original name
Specially developed LR-0 reactor graphite environment for gen IV reactor support and cross-section measurement
Authors
PELTAN, Tomáš (guarantor), Eva VILIMOVÁ, Tomáš CZAKOJ, Zdeněk MATĚJ (203 Czech Republic, belonging to the institution), Filip MRAVEC (203 Czech Republic), František CVACHOVEC (203 Czech Republic), Jan ŠIMON, Vlastimil JIŘÍČEK and Michal KOŠŤÁL
Edition
Real Collegio, ANIMMA 2023 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications, p. 1-8, 8 pp. 2023
Publisher
EDP Sciences
Other information
Language
English
Type of outcome
Stať ve sborníku
Field of Study
20201 Electrical and electronic engineering
Confidentiality degree
není předmětem státního či obchodního tajemství
Publication form
electronic version available online
References:
RIV identification code
RIV/00216224:14330/23:00133901
Organization unit
Faculty of Informatics
ISSN
Keywords in English
LR-0 reactor; a research reacto; graphite; crosssection; neutron leakage spectra; californium leakage spectrum
Změněno: 21/10/2024 09:12, doc. RNDr. Zdeněk Matěj, Ph.D.
Abstract
V originále
This paper is focused on the development of the experimental environment connected to reactor graphite. Regarding its very good neutronic and mechanical properties, graphite will be very important in some new reactor designs, such as high-temperature or molten salt SMR reactors. These new reactor concepts require a new experimental environment as support for further research. In the laboratories of the Research Centre Řež and at the LR-0 reactor, the new experimentally validated graphite environment was created. This large graphite insertion is the largest graphite mono-block, which is possible to assemble at the LR-0 reactor. Sets of experiments for measuring reaction rates of different activation detectors for neutron field mapping were performed. This approach was used for thermal and epithermal region descriptions. For the fast neutron spectrum evaluation, the stilbene scintillation detector was used. All parameters, such as criticality height of moderator level, neutron spectrum, and other parameters for all experiments, were performed using Monte Carlo neutronic codes Serpent and MCNP. The obtained results were finally compared to the measurement of neutron leakage spectra from the graphite cube and graphite cylinder. These specially developed graphite-shaped neutron fields, reactor insertions, and external cube and cylinder with Cf neutron source can be used in the future for validation of not only materials used in SMR reactors but for arbitrary cross-section verification.
Links
MUNI/A/1586/2023, interní kód MU |
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