Published August 1983 | Version v1
Report Open

Status of fuel element technology for plate type dispersion fuels with high uranium density

  • 1. NUKEM (Germany)
  • 2. Kernforschungszentrum Karlsruhe (Germany)

Description

A number of about 20 Material Test and Research Reactors in Germany and abroad is supplied with fuel elements by the company NUKEM. The power of these reactors differs widely ranging from up to about 100 MW. Consequently, the uranium density of the fuel elements in the meat varies considerably depending on the reactor type and is usually within the range from 0.4 to 1.3 g U/cm3 if HEU is used. In order to convert these reactors to lower uranium enrichment (19.75% 235-U) extensive work is carried out at NUKEM since about two years with the goal to develop fuel elements with high U-density. This work is sponsored by the German Ministry for Research and Technology in the frame of the AF-program. This paper reports on the present state of development for fuel elements with high U-density fuels at NUKEM is reported. The development works were so far concentrated on UAlx, U3O8 and UO2 fuels which will be described in more detail. In addition fuel plates with new fuels like e.g. U-Si or U-Fe compounds are developed in collaboration with KfK. The required uranium densities for some typical reactors with low, medium, and high power are listed allowing a comparison of HEU and LEU uranium density requirements. The 235-U-content in the case of LEU is raised by 18%. Two different meat thicknesses are considered: Standard thickness of 0.5 mm; and increased thickness of 0.76 mm. From this data compilation the objective follows: in the case of conversion to LEU (19.75% 235-U-enrichment), uranium densities have to be made available up to 24 gU/cm3 meat for low power level reactors, up to 33 gU/cm3 meat for medium power level reactors, and between 5.75 and 7.03 g/cm3 meat for high power level reactors according to this consideration

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Part of:
Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology

Additional details

Publishing Information

Imprint Title
Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology
Imprint Pagination
671 p.
Journal Page Range
p. 201-221
Report number
ANL/RERTR/TM--3

Conference

Title
International meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR)
Dates
12-14 Nov 1980
Place
Argonne, IL (United States)

Optional Information

Notes
3 refs, 15 figs
Secondary number(s)
CONF--801144; INIS-XA-C--021