D 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
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