Radiation damage analysis of the first generation VVER spent nuclear fuel casks

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21730%2F24%3A00372709" target="_blank" >RIV/68407700:21730/24:00372709 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/49777513:23220/24:43969971

Výsledek na webu

<a href="https://doi.org/10.1016/j.anucene.2023.110214" target="_blank" >https://doi.org/10.1016/j.anucene.2023.110214</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2023.110214" target="_blank" >10.1016/j.anucene.2023.110214</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Radiation damage analysis of the first generation VVER spent nuclear fuel casks

Popis výsledku v původním jazyce

Radiation damage can be assessed by displacements per atom (DPA). DPA calculations can be performed with flux conversion functions for iron or low alloy steels by ASTM or IRDFF standards. However, these standards cannot be applied for higher alloy steels or for materials with arbitrary chemical composition. In these circumstances, cross sections for arc-DPA and NRT-DPA definitions can be used. In the paper, the radiation damage analysis for determining DPA based on all available nuclear data is presented. The analysis was carried out for a first generation of VVER-440 dual purpose spent fuel cask. This spent fuel cask is one of the oldest cast ductile iron casks manufactured and its original lifetime will expire soon. Monte Carlo codes MCNP6 and Serpent 2 are both used for the radiation damage study to find out if radiation damage of the cask does not represent a major issue in its lifetime.

Název v anglickém jazyce

Radiation damage analysis of the first generation VVER spent nuclear fuel casks

Popis výsledku anglicky

Radiation damage can be assessed by displacements per atom (DPA). DPA calculations can be performed with flux conversion functions for iron or low alloy steels by ASTM or IRDFF standards. However, these standards cannot be applied for higher alloy steels or for materials with arbitrary chemical composition. In these circumstances, cross sections for arc-DPA and NRT-DPA definitions can be used. In the paper, the radiation damage analysis for determining DPA based on all available nuclear data is presented. The analysis was carried out for a first generation of VVER-440 dual purpose spent fuel cask. This spent fuel cask is one of the oldest cast ductile iron casks manufactured and its original lifetime will expire soon. Monte Carlo codes MCNP6 and Serpent 2 are both used for the radiation damage study to find out if radiation damage of the cask does not represent a major issue in its lifetime.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10304 - Nuclear physics

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

Annals of Nuclear Energy

ISSN

0306-4549

e-ISSN

1873-2100

Svazek periodika

196

Číslo periodika v rámci svazku

February

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

8

Strana od-do

—

Kód UT WoS článku

001115121100001

EID výsledku v databázi Scopus

2-s2.0-85176602062