The molded block fuel element (FE) also called monolith is a molded body, consisting of a substantially isotropic highly crystalline graphite matrix, fuel regions within the same matrix and cooling channels. The fuel regions contain the fuel in the form of coated particles which are well bonded to the remaining graphite matrix, so that both parts of the block form a monolithic structure. The monolith meets the requirements for the very high temperature reactors attaining helium outlet temperatures above 1000°C. To fabricate the molded blocks FE demonstration plant was erected and put into operation. The equipment worked without malfunction. The produced block FEs meet the specifications of GA machined block FEs. All specimens and block segments irradiated at temperature up to 1600°C and max. fast fluence E > 0, 1 MeV of 11×1021 n/cm2 show perfect behaviour without any damage.
Skip Nav Destination
Fourth International Topical Meeting on High Temperature Reactor Technology
September 28–October 1, 2008
Washington, DC, USA
Conference Sponsors:
- ASME
ISBN:
978-0-7918-4855-5
PROCEEDINGS PAPER
Fabrication, Properties and Irradiation Performance of Molded Block Fuel Elements for HTGRs
Milan F. Hrovat,
Milan F. Hrovat
ALD Vacuum Technologies GmbH, Hanau, Germany
Search for other works by this author on:
Karl-H. Grosse,
Karl-H. Grosse
ALD Vacuum Technologies GmbH, Hanau, Germany
Search for other works by this author on:
Richard Seemann
Richard Seemann
ALD Vacuum Technologies GmbH, Hanau, Germany
Search for other works by this author on:
Milan F. Hrovat
ALD Vacuum Technologies GmbH, Hanau, Germany
Karl-H. Grosse
ALD Vacuum Technologies GmbH, Hanau, Germany
Richard Seemann
ALD Vacuum Technologies GmbH, Hanau, Germany
Paper No:
HTR2008-58025, pp. 613-618; 6 pages
Published Online:
July 1, 2009
Citation
Hrovat, MF, Grosse, K, & Seemann, R. "Fabrication, Properties and Irradiation Performance of Molded Block Fuel Elements for HTGRs." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2. Washington, DC, USA. September 28–October 1, 2008. pp. 613-618. ASME. https://doi.org/10.1115/HTR2008-58025
Download citation file:
12
Views
Related Proceedings Papers
Related Articles
HTR-TN Achievements and Prospects for Future Developments
J. Eng. Gas Turbines Power (June,2011)
Three-Dimensional Sintering of Two-Component Metal Powders With
Stationary and Moving Laser Beams
J. Heat Transfer (February,2000)
Large-Scale Modeling of Damage and Failure of Nuclear Graphite Moderated Reactor
J. Pressure Vessel Technol (June,2022)
Related Chapters
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Preparation of TiC Nanopowder by Mechanical Alloying Process
International Conference on Mechanical and Electrical Technology, 3rd, (ICMET-China 2011), Volumes 1–3
Long.Term Reactivity Change and Control: On.Power Refuelling
Fundamentals of CANDU Reactor Physics