Neutronic performance of VVER-1200 reactor with advanced fuel and cladding materials

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F23%3A00364156" target="_blank" >RIV/68407700:21340/23:00364156 - isvavai.cz</a>

Výsledek na webu

<a href="https://doi.org/10.1016/j.nucengdes.2023.112216" target="_blank" >https://doi.org/10.1016/j.nucengdes.2023.112216</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nucengdes.2023.112216" target="_blank" >10.1016/j.nucengdes.2023.112216</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Neutronic performance of VVER-1200 reactor with advanced fuel and cladding materials

Popis výsledku v původním jazyce

Nuclear reactor operation and safety are connected with a nuclear fuel design and its material and geometry properties. An increase in nuclear safety is therefore based on a neutronic and thermal analysis of the materials used in a core. This paper analyzes neutronic properties of a VVER-1200 fuel assembly with alternate fuel and cladding materials that consider Accident Tolerant or Advanced Technology Fuels (ATF). The ATF nuclear fuel development started with the post-Fukushima efforts and its main purpose is a reduction of the high-temperature hydrogen production from the zirconium water reaction. Five ATF cladding candidates with reference Zr-based alloy are studied in this paper as well as six ATF fuel candidates together with an additional standard UO2 reference case. The results are analysed based on the multiplication characteristics, reactivity feedbacks, and spent nuclear fuel composition.

Název v anglickém jazyce

Neutronic performance of VVER-1200 reactor with advanced fuel and cladding materials

Popis výsledku anglicky

Nuclear reactor operation and safety are connected with a nuclear fuel design and its material and geometry properties. An increase in nuclear safety is therefore based on a neutronic and thermal analysis of the materials used in a core. This paper analyzes neutronic properties of a VVER-1200 fuel assembly with alternate fuel and cladding materials that consider Accident Tolerant or Advanced Technology Fuels (ATF). The ATF nuclear fuel development started with the post-Fukushima efforts and its main purpose is a reduction of the high-temperature hydrogen production from the zirconium water reaction. Five ATF cladding candidates with reference Zr-based alloy are studied in this paper as well as six ATF fuel candidates together with an additional standard UO2 reference case. The results are analysed based on the multiplication characteristics, reactivity feedbacks, and spent nuclear fuel composition.

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/TK03020034" target="_blank" >TK03020034: Využití pokročilých materiálů pro nové typy jaderného paliva</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

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

1872-759X

Svazek periodika

405

Číslo periodika v rámci svazku

04

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

11

Strana od-do

—

Kód UT WoS článku

000942085400001

EID výsledku v databázi Scopus

2-s2.0-85148003488