Benchmark on neutron flux spatial effects in subcritical system based on IRT-4 M fuel for near-core positions

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F21%3A00348305" target="_blank" >RIV/68407700:21340/21:00348305 - isvavai.cz</a>

Výsledek na webu

<a href="https://doi.org/10.1016/j.anucene.2021.108231" target="_blank" >https://doi.org/10.1016/j.anucene.2021.108231</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2021.108231" target="_blank" >10.1016/j.anucene.2021.108231</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Benchmark on neutron flux spatial effects in subcritical system based on IRT-4 M fuel for near-core positions

Popis výsledku v původním jazyce

The paper presents a benchmark aimed at assessing the accuracy of Monte Carlo codes to simulate the neutron detector response in near-core geometry of a subcritical water-moderated reactor. The experiment included six levels of subcriticality with keff from 0.93 to 0.996, and four fixed detector positions. Studied parameters included: first, the prediction of the change in detector response with the change in subcritical multiplication at a given detector position; second, the prediction of the change in neutron flux spatial distribution; third, the effectiveness of calculated correction factors to decrease the inconsistency in reactivity determined using detectors at various locations. Calculations were performed in MCNP6 code using two nuclear data sets. Both the general source and the eigenvalue (criticality) mode of calculation were studied. Finally, the effect of the offset between the calculated and experimentally determined critical condition on the prediction of detector response in the subcritical state was analysed.

Název v anglickém jazyce

Benchmark on neutron flux spatial effects in subcritical system based on IRT-4 M fuel for near-core positions

Popis výsledku anglicky

The paper presents a benchmark aimed at assessing the accuracy of Monte Carlo codes to simulate the neutron detector response in near-core geometry of a subcritical water-moderated reactor. The experiment included six levels of subcriticality with keff from 0.93 to 0.996, and four fixed detector positions. Studied parameters included: first, the prediction of the change in detector response with the change in subcritical multiplication at a given detector position; second, the prediction of the change in neutron flux spatial distribution; third, the effectiveness of calculated correction factors to decrease the inconsistency in reactivity determined using detectors at various locations. Calculations were performed in MCNP6 code using two nuclear data sets. Both the general source and the eigenvalue (criticality) mode of calculation were studied. Finally, the effect of the offset between the calculated and experimentally determined critical condition on the prediction of detector response in the subcritical state was analysed.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10304 - Nuclear physics

Projekt

<a href="/cs/project/EF16_013%2F0001790" target="_blank" >EF16_013/0001790: Posílení a rozvoj výzkumu na ČVUT v Praze s využitím výzkumné infrastruktury VR-1- Školní reaktor pro výzkumnou činnost</a><br>

Návaznosti

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

Rok uplatnění

2021

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

157

Číslo periodika v rámci svazku

7

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

11

Strana od-do

—

Kód UT WoS článku

000644696400020

EID výsledku v databázi Scopus

2-s2.0-85102579811