DPA calculation for the first generation of VVER-440 dual purpurose cask

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F23%3A43970614" target="_blank" >RIV/49777513:23220/23:43970614 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

DPA calculation for the first generation of VVER-440 dual purpurose cask

Popis výsledku v původním jazyce

Radiation damage can be assessed by displacements per atom. DPA calculations can be performed with flux conversion functions for stainless steels by ASTM or IRDFF standards or with damage cross sections for arc-DPA and NRT-DPA definitions. In the paper, DPA calculations of borated steel, aluminum alloy and cast iron as the most affected materials in the first generation of VVER-440 dual purpose spent fuel cask is presented. DPA rate calculated by damage energy cross sections from BROND, CENDL, ENDF/B, JEFF, JENDL and RUSFOND libraries and functions from ASTM and IRDFF standards were compared on simplified spent fuel cask model with MCNP6 calculation code. The aim of the paper is to present which cross sections are conservative for various types of materials and how long-term storage would affect total DPA for the cask materials.

Název v anglickém jazyce

DPA calculation for the first generation of VVER-440 dual purpurose cask

Popis výsledku anglicky

Radiation damage can be assessed by displacements per atom. DPA calculations can be performed with flux conversion functions for stainless steels by ASTM or IRDFF standards or with damage cross sections for arc-DPA and NRT-DPA definitions. In the paper, DPA calculations of borated steel, aluminum alloy and cast iron as the most affected materials in the first generation of VVER-440 dual purpose spent fuel cask is presented. DPA rate calculated by damage energy cross sections from BROND, CENDL, ENDF/B, JEFF, JENDL and RUSFOND libraries and functions from ASTM and IRDFF standards were compared on simplified spent fuel cask model with MCNP6 calculation code. The aim of the paper is to present which cross sections are conservative for various types of materials and how long-term storage would affect total DPA for the cask materials.

Druh

O - Ostatní výsledky

CEP obor

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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

2023

Kód důvěrnosti údajů

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