Published October 2012 | Version v1
Journal article

Improvements in the fabrication of HTR fuel elements

  • 1. NUKEM Technologies GmbH, Industriestrasse 13, 63755 Alzenau (Germany)
  • 2. FNAG Furnaces Nuclear Applications Grenoble S.A.S., Wilhelm-Rohn Strasse 35, 63450 Hanau (Germany)
  • 3. ALD Vacuum Technologies GmbH, Wilhelm-Rohn Strasse 35, 63450 Hanau (Germany)

Description

The application of High Temperature Reactor (HTR) Technology in the course of the continuously increasing world wide demand on energy is taken more and more under serious consideration in the power supply strategy of various countries. Especially for the emerging nations the HTR Technology has become of special interest because of its inherent safety feature and due to the alternative possibilities of applications, e.g. in the production of liquid hydrocarbons or the alternative application in H2 generation. The HTR fuel in its various forms (spheres or prismatic fuel blocks) is based on small fuel kernels of about 500 μm in diameter. Each of these uranium oxide or carbide kernels are coated with several layers of pyrocarbon (PyC) as well as an additional silicon carbide (SiC) layer. While the inner pyrocarbon layer is porous and capable to absorb gaseous fission products, the dense outer PyC layer forms the barrier against fission product release. The SiC layer improves the mechanical strengths of this barrier and considerably increases the retention capacity for solid fission products that tent to diffuse at these temperatures. Especially the high quality German LEU TRISO spherical fuel based on the NUKEM design, has demonstrated the best fission product release rate, particular at high temperatures. The ∼10% enriched uranium triple-coated particles are embedded in a moulded graphite sphere. A fuel sphere consists of approximately 9 g of uranium (some 15,000 particles) and has a diameter of 60 mm. As the unique safety features, especially the inherent safety of the HTR is based on the fuel design, this paper shall reflect the complexity but also developments and economical aspects of the fabrication processes for HTR fuel elements.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2011.10.036

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2011.10.036;
PII
S0029-5493(11)00909-5;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
251
Journal Page Range
p. 239-243
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
5. international topical meeting on high temperature reactor technology
Acronym
HTR 2010
Dates
18-20 Oct 2010
Place
Prague (Czech Republic)

Optional Information

Copyright
Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.