Direkt zum Inhalt springen
Deutsch English
The Neutron Source
Science
Industry
News and Events
User Office

News

Events

Conferences

SANS-Workshop 21./22. Juni
June 21 - June 22

Seminars

Expansion of Research Facilities at the NIST Center for Neutron Research
May 21 14:45 - 15:45

The NIST Center for Neutron Research (NCNR) has just returned to full-time operation after...
Commissioning of the CASCADE detector at MIRA
June 04 14:45 - 15:45

Structural and dynamic study of several magnetic systems by means of Neutron Resonant Spin Echo techniques
June 11 14:45 - 15:45

“ZETA” is a Neutron Resonant Spin Echo (NRSE) option which is currently installed on the thermal...
more Events ->

Uranium Silicide-Aluminium Dispersion

FRM II's high thermal neutron flux density of approx. 8x1014cm-2s-1 is due to the compact core concept and the use of an uranium silicide-aluminium dispersion.

To achieve to duration cycle of approx. 52 days the fuel element must contain an adequate mass of the uranium isotope 235U. After this cycle at a nominal thermal power of 20MW the fuel element has to be replaced by a new one.

  • On the one side highly enriched uranium must be used (enrichment factor approx. 93% 235U and approx. 7% 238U) for the fuel element for containing an adequate mass of this uranium isotope. 238U absorbs neutrons very good and changes into plutonium.
  • On the other side the density of this highly enriched uranium must be relatively high, too.

That's the reason why FRM II's compact core concept includes new developed nuclear fuel based on uranium silicide-aluminium dispersion. In order to homogenise the power and fission density, the uranium content in the outer zone of each fuel plate is reduced from 3gcm-3 to 1,5gcm-3. The reactor core contains approx. 8,1kg uranium in total.

FRM II's new fuel elements include new technical know-how. Despite these innovations the nuclear safety must be and is ensured. Fuel elements of this geometry with involuted, curved fuel plates have been tested at the high-flux research reactors HFR (Grenoble, France) and HFIR (Oak Ridge, USA) for many years. Their power density or velocity of the cooling water is comparable to these characteristics of FRM II.

The new developed uranium silicide-aluminium dispersion fuel elements have been successfully tested in international programs. To ensure a highest level of safety the fuel elements will be tested again before operation starts at FRM II.

uranfuel
U3Si2 particle in the Al matrix, taken in the region of the test-plate with a fission density of 12x1021fcm3 in the fuel particles. The morphology of the fission gas bubbles in the particle is as expected. Moreover, the thickness of the U-Al interdiffusion layer (light-gray area at the grain-boundary) is of the order of 6μm and in good accordance with theory.