Optimizing spent nuclear fuel cask loading for VVER-440 fuel

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F24%3A43973529" target="_blank" >RIV/49777513:23220/24:43973529 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S1738573324003292" target="_blank" >https://www.sciencedirect.com/science/article/pii/S1738573324003292</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.net.2024.07.014" target="_blank" >10.1016/j.net.2024.07.014</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Optimizing spent nuclear fuel cask loading for VVER-440 fuel

Popis výsledku v původním jazyce

The paper explores the management of spent nuclear fuel, focusing on dual-purpose spent fuel casks used to store and transport spent nuclear fuel from VVER-440 reactors. The main goal is to optimize spent fuel cask loading by developing an extensive methodology supported by a powerful tool. Using a multiple-zoning strategy, cooler outside fuel assemblies protect radiation sources from the hotter inner assemblies. An effective tool based on adjoint particle flux calculations is the recently developed OPOS-440 calculation code. This code allows for optimizing the loading pattern and determining dose rates surrounding the spent nuclear fuel cask for a selected fuel loading. The code also thoroughly demonstrates how different fuel assemblies affect the dose rate. These findings have real-world implications for reactor operations, including optimizing cask loading and supporting the licensing procedure for novel fuel types in already-existing spent fuel casks.

Název v anglickém jazyce

Optimizing spent nuclear fuel cask loading for VVER-440 fuel

Popis výsledku anglicky

The paper explores the management of spent nuclear fuel, focusing on dual-purpose spent fuel casks used to store and transport spent nuclear fuel from VVER-440 reactors. The main goal is to optimize spent fuel cask loading by developing an extensive methodology supported by a powerful tool. Using a multiple-zoning strategy, cooler outside fuel assemblies protect radiation sources from the hotter inner assemblies. An effective tool based on adjoint particle flux calculations is the recently developed OPOS-440 calculation code. This code allows for optimizing the loading pattern and determining dose rates surrounding the spent nuclear fuel cask for a selected fuel loading. The code also thoroughly demonstrates how different fuel assemblies affect the dose rate. These findings have real-world implications for reactor operations, including optimizing cask loading and supporting the licensing procedure for novel fuel types in already-existing spent fuel casks.

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/TN02000012" target="_blank" >TN02000012: Centrum pokročilých jaderných technologií II</a><br>

Návaznosti

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

Rok uplatnění

2024

Kód důvěrnosti údajů

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

Název periodika

Nuclear Engineering and Technology

ISSN

1738-5733

e-ISSN

2234-358X

Svazek periodika

56

Číslo periodika v rámci svazku

12

Stát vydavatele periodika

KP - Korejská lidově demokratická republika

Počet stran výsledku

7

Strana od-do

5048-5054

Kód UT WoS článku

001359511100001

EID výsledku v databázi Scopus

2-s2.0-85198544453