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

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F23%3A43966652" target="_blank" >RIV/49777513:23220/23:43966652 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/00216224:14330/23:00133900 RIV/26722445:_____/23:N0000007

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S0306454922005874?via%3Dihub" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0306454922005874?via%3Dihub</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2022.109557" target="_blank" >10.1016/j.anucene.2022.109557</a>

Jazyk výsledku

angličtina

Název v původním jazyce

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

Popis výsledku v původním jazyce

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 wellcharacterised 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.

Název v anglickém jazyce

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

Popis výsledku anglicky

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 wellcharacterised 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.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

<a href="/cs/project/TK01030103" target="_blank" >TK01030103: Ex-core měření neutronového toku pro reaktory IV. generace</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2023

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název periodika

ANNALS OF NUCLEAR ENERGY

ISSN

0306-4549

e-ISSN

1873-2100

Svazek periodika

181

Číslo periodika v rámci svazku

February 2023

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

11

Strana od-do

—

Kód UT WoS článku

000890345200001

EID výsledku v databázi Scopus

2-s2.0-85141502988