Recent Findings from RWTH Aachen University Provides New Insights into Nuclear Engineering (Computational analysis of modern HTGR fuel performance and fission product release during the HFR-EU1 irradiation experiment)
By a News Reporter-Staff News Editor at Journal of Engineering -- Data detailed on Nuclear Engineering have been presented. According to news originating from Aachen, Germany, by VerticalNews correspondents, research stated, "Various countries engaged in the development and fabrication of modern HTGR fuel have initiated activities of modeling the fuel and fission product release behavior with the aim of predicting the fuel performance under HTGR operating and accident conditions. Verification and validation studies are conducted by code-to-code benchmarking and code-to-experiment comparisons as part of international exercises."
Our news journalists obtained a quote from the research from RWTH Aachen University, "The methodology developed in Germany since the 1980s represents valuable and efficient tools to describe fission product release from spherical fuel elements and TRISO fuel performance, respectively, under given conditions. Continued application to new results of irradiation and accident simulation testing demonstrates the appropriateness of the models in terms of a conservative estimation of the source term as part of interactions with HTGR licensing authorities. Within the European irradiation testing program for HTGR fuel and as part of the former EU RAPHAEL project, the HFR-EU1 irradiation experiment explores the potential for high performance of the presently existing German and newly produced Chinese fuel spheres under defined conditions up to high burnups. The fuel irradiation was completed in 2010. Test samples are prepared for further postirradiation examinations (PIE) including heatup simulation testing in the KUFA-II furnace at the JRC-ITU. Karlsruhe, to be conducted within the on-going ARCHER Project of the European Commission. The paper will describe the application of the German computer models to the HFR-EU1 irradiation test and compare within the preliminary experimental results as well as with previously conducted, true predictive calculations."
According to the news editors, the research concluded: "Furthermore, results will be compared with the German code development STACY that extends the earlier codes toward new features."
For more information on this research see: Computational analysis of modern HTGR fuel performance and fission product release during the HFR-EU1 irradiation experiment. Nuclear Engineering and Design, 2014;273():85-97. Nuclear Engineering and Design can be contacted at: Elsevier Science Sa, PO Box 564, 1001 Lausanne, Switzerland. (Elsevier - www.elsevier.com; Nuclear Engineering and Design - www.elsevier.com/wps/product/cws_home/505661)
The news correspondents report that additional information may be obtained from K. Verfondern, Rhein Westfal TH Aachen, Chair Reactor Safety & Reactor Technol, D-52072 Aachen, Germany. Additional authors for this research include A. Xhonneux, H. Nabielek and H.J. Allelein.
Keywords for this news article include: Aachen, Germany, Europe, Nuclear Engineering
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