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research article

Preparation for commissioning of materials detritiation facility at Culham Science Centre

Kresina, Michal
•
Decanis, Christelle
•
Newman, Mark
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November 1, 2018
Fusion Engineering And Design

The Materials Detritiation Facility has been designed to thermally treat solid non-combustible radioactive waste produced during operations of the Joint European Torus (JET) that is classified as Intermediate Level Waste in the UK due to its tritium inventory (> 12 kBq/g). The waste will be thermally treated in a retort furnace at temperatures up to 1000 degrees C under a flowing air atmosphere to reduce its tritium inventory sufficiently to allow its disposal at a lower waste category via existing disposal routes. The gaseous flow from the furnace will be processed via a bubbler system, where released tritium will be trapped in water. Commissioning of the facility will be divided into two main parts: inactive and active. The main purpose of the inactive commissioning is to verify that all components and safety systems of the facility are installed, tested and operated properly and within their operational limits. Several trials of the furnace with non-radioactive materials will be performed to verify its temperature profile, and to verify operation of the gaseous process line. During the active commissioning, small amounts of tritium-contaminated material will be introduced into the facility and used for active trials. The tritium inventory in this material has been selected based on the As low as reasonably practicable (ALARP) principle, to ensure that the activity levels are sufficient to fully test the control instrumentation and pose minimal risk to operators during commissioning. Overall, four active trials will be performed with carbon-based and Inconel materials with total tritium inventories of 1MBq, 3GBq, 20GBq and 26GBq. Tritium levels in the bubblers as well as in aerial discharge from the facility will be monitored. Furthermore, all materials used in the active trials will be sampled and analyzed to verify the performance of the process and confirm that a major part of tritium inventory can be removed from materials by the process.

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Type
research article
DOI
10.1016/j.fusengdes.2018.05.019
Web of Science ID

WOS:000452575300102

Author(s)
Kresina, Michal
Decanis, Christelle
Newman, Mark
Clements, Christopher
Wilson, Ian
Coombs, David
Utard, Aurelien
Canas, Daniel
Abduallev, S.
Abhangi, M.
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Date Issued

2018-11-01

Published in
Fusion Engineering And Design
Volume

136

Start page

1391

End page

1395

Subjects

Nuclear Science & Technology

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tritiated waste

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detritiation

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thermal processing

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non-combustible waste

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commissioning

Note

13th International Symposium on Fusion Nuclear Technology (ISFNT), Sep 25-29, 2017, Kyoto, JAPAN

Editorial or Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
SPC  
Available on Infoscience
September 20, 2019
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/161352
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