Characterisation of neutron field in large graphite insertion
in special core of the LR-0 reactor

J 2023

Characterisation of neutron field in large graphite insertion in special core of the LR-0 reactor

PELTAN, Tomáš, Eva VILÍMOVÁ, Tomáš CZAKOJ, Zdeněk MATĚJ, Filip MRAVEC et. al.

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

Language

English

Type of outcome

Článek v odborném periodiku

Field of Study

20201 Electrical and electronic engineering

Country of publisher

Netherlands

Confidentiality degree

není předmětem státního či obchodního tajemství

References:

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

Změněno: 21/10/2024 09:11, doc. RNDr. Zdeněk Matěj, Ph.D.

Abstract

V originále

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.

Links

MUNI/A/1586/2023, interní kód MU

Name: Aplikovaný výzkum na FI: Forenzní aspekty kritických infrastruktur, aplikovaná kryptografie, kyberbezpečnostní cvičení, algoritmy plánování v logistice a pro zpracování dat z fyzikálních sensorů

Investor: Masaryk University, Applied research at FI: Forensic aspects of critical infrastructures, applied cryptography, cybersecurity trainings, scheduling algorithms logistics and algorithms for physical sensors

Citovat

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.

@article{2387999,
   author = {Peltan, Tomáš and Vilímová, Eva and Czakoj, Tomáš and Matěj, Zdeněk and Mravec, Filip and Cvachovec, František and Šimon, Jan and Juříček, Vlastimil and Košťál, Michal},
   article_location = {UNITED STATES},
   article_number = {1},
   doi = {http://dx.doi.org/10.1016/j.anucene.2022.109557},
   keywords = {Graphite cross-section validation; Graphite shaped neutron field; Reference neutron field; Monte Carlo Simulation},
   language = {eng},
   issn = {0306-4549},
   journal = {ANNALS OF NUCLEAR ENERGY},
   title = {Characterisation of neutron field in large graphite insertion in special core of the LR-0 reactor},
   url = {https://www.sciencedirect.com/science/article/pii/S0306454922005874},
   volume = {181},
   year = {2023}
}

TY  - JOUR
ID  - 2387999
AU  - Peltan, Tomáš - Vilímová, Eva - Czakoj, Tomáš - Matěj, Zdeněk - Mravec, Filip - Cvachovec, František - Šimon, Jan - Juříček, Vlastimil - Košťál, Michal
PY  - 2023
TI  - Characterisation of neutron field in large graphite insertion in special core of the LR-0 reactor
JF  - ANNALS OF NUCLEAR ENERGY
VL  - 181
IS  - 1
SP  - 1-11
EP  - 1-11
PB  - PERGAMON-ELSEVIER SCIENCE LTD
SN  - 03064549
KW  - Graphite cross-section validation
KW  - Graphite shaped neutron field
KW  - Reference neutron field
KW  - Monte Carlo Simulation
UR  - https://www.sciencedirect.com/science/article/pii/S0306454922005874
N2  - 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.
ER  -

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. \textit{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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