Accident testing of High Temperature Reactor fuel elements with the KüFA device

Author

Seeger, O. ; Laurie, M. ; Bottomley, P.D.W. ; Ferreira-Teixeira, A.E. ; van Winckel, S. ; Rondinella, V.V. ; Allelein, Hans-Josef

Author_Institution

Joint Res. Centre, Eur. Comm., Eggenstein-Leopoldshafen, Germany

fYear

2013

fDate

23-27 June 2013

Firstpage

1

Lastpage

7

Abstract

The High Temperature Reactor (HTR) is characterised by an advanced design with passive safety features. Fuel elements are constituted by a graphite matrix containing sub-mm-sized fuel particles with TRi-ISOtropic (TRISO) coating, designed to provide high fission product retention. During a loss of coolant accident scenario in a HTR the maximum temperature is foreseen to be in the range of 1600-1650 °C, remaining well below the melting point of the fuel.

Keywords

fission reactor accidents; fission reactor coolants; fission reactor design; fission reactor fuel; KuFA device; TRi-ISOtropic coating; accident testing; fission product retention; graphite matrix; high temperature reactor fuel elements; loss-of-coolant accident scenario; passive safety; submm-sized fuel particles; temperature 1600 degC to 1650 degC; Distance measurement; Fuels; Furnaces; Heating; Maintenance engineering; Standards; Testing; Fission Product Release; Fuel Accident Testing; Gamma Spectroscopy; HTR; ICP-MS; KüFA; Pebble This;

fLanguage

English

Publisher

ieee

Conference_Titel

Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2013 3rd International Conference on

Conference_Location

Marseille

Print_ISBN

978-1-4799-1046-5

Type

conf

DOI

10.1109/ANIMMA.2013.6728004

Filename

6728004