Tungsten Detritation using MSO Technology

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F25%3AN0000105" target="_blank" >RIV/26722445:_____/25:N0000105 - isvavai.cz</a>

Result on the web

<a href="https://www.djs.si/nene2024proceedings/pdf/NENE2024_1015.pdf" target="_blank" >https://www.djs.si/nene2024proceedings/pdf/NENE2024_1015.pdf</a>

DOI - Digital Object Identifier

—

Result language

angličtina

Original language name

Tungsten Detritation using MSO Technology

Original language description

In the fusion energy industry, tritium is used as a fuel element and is essential for the future operation of the first generation of fusion power plants. Tritium is very rare in nature and is currently recovered from the coolant of heavy water nuclear reactors. The recovery of tritium is a complex and costly process involving several steps, from the separation of tritium from heavy water to its purification and storage, which is severely limited by the low half-life of tritium. Tritium management and methods for its recovery and eventual recycling remain a challenging issue. Efficient tritium management is essential for the safe and economic operation of future fusion power plants. The operation of experimental fusion reactors has demonstrated the production of radioactive waste in the form of various tritium-contaminated materials. The management of tritium-contaminated materials has received considerable attention in research into the energetic use of thermonuclear fusion. A significant type of radioactive waste that will be generated during the lifetime of a fusion power plant is tritiated tungsten dust. In this paper, experiments have been carried out to determine the effectiveness of the Molten Salt Oxidation (MSO) process in recovering tritium from contaminated tungsten pellets simulating tritiated tungsten dust. Analysis of the output showed successful capture of tritium in the form of tritiated water and determined the efficiency of the process under defined conditions. A two-stage water condensation system was used to capture tritium. Tritium capture efficiencies range from 10 to 37 % with a median efficiency of 13.82 %. More than 90 % of the activity was captured in the first stage of the condensation system. This process has proven to be an effective way to treat and recycle tritium contaminated materials. From the data obtained, a possible approach to the treatment of the expected radioactive waste from fusion power plants is presented. The use of MSO technology for the purpose of tungsten detritation appears appropriate and its effectiveness has been experimentally demonstrated. The next steps include extensive testing in different operational settings to optimize the process for industrial applications.

Czech name

—

Czech description

—

Type

D - Article in proceedings

CEP classification

—

OECD FORD branch

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Project

—

Continuities

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Publication year

2025

Confidentiality

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

Article name in the collection

Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 9-12, 2024

ISBN

978-961-6207-59-1

ISSN

—

e-ISSN

—

Number of pages

9

Pages from-to

1-9

Publisher name

—

Place of publication

Portorož, Slovenia

Event location

Portorož, Slovenia

Event date

Sep 9, 2025

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

001453270200075