Petrov, B. Y.; Kuijper, J. C.; Oppe, J.; De Haas, J. B. M.
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)2012
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)2012
AbstractAbstract
[en] This paper contains results of the analysis of the pebble-bed high temperature gas-cooled PUMA reactor loaded with plutonium and minor actinide (Pu/MA) fuel. Starting from knowledge and experience gained in the Euratom FP5 projects HTR-N and HTR-N1, this study aims at demonstrating the potential of high temperature reactors to utilize or transmute Pu/MA fuel. The work has been performed within the Euratom FP6 project PUMA. A number of different fuel types and fuel configurations have been analyzed and compared with respect to incineration performance and safety-related reactor parameters. The results show the excellent plutonium and minor actinide burning capabilities of the high temperature reactor. The largest degree of incineration is attained in the case of an HTR fuelled by pure plutonium fuel as it remains critical at very deep burnup of the discharged pebbles. Addition of minor actinides to the fuel leads to decrease of the achievable discharge burnup and therefore smaller fraction of actinides incinerated during reactor operation. The inert-matrix fuel design improves the transmutation performance of the reactor, while the 'wallpaper' fuel does not have advantage over the standard fuel design in this respect. After 100 years of decay following the fuel discharge, the total amount of actinides remains almost unchanged for all of the fuel types considered. Among the plutonium isotopes, only the amount of Pu-241 is reduced significantly due to its relatively short half-life. (authors)
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2012; 15 p; American Nuclear Society - ANS; La Grange Park, IL (United States); PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education; Knoxville, TN (United States); 15-20 Apr 2012; ISBN 978-0-89448-085-9; ; Country of input: France; 12 refs.
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Book
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Conference
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ACTINIDE NUCLEI, ACTINIDES, ALPHA DECAY RADIOISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CHEMICAL REACTIONS, ELEMENTS, ENERGY SOURCES, EUROPEAN UNION, EVEN-ODD NUCLEI, FUELS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HEAVY NUCLEI, HOMOGENEOUS REACTORS, INTERNATIONAL ORGANIZATIONS, ISOTOPES, MATERIALS, MEASURING INSTRUMENTS, METALS, NUCLEI, OPERATION, OXIDATION, PLUTONIUM ISOTOPES, RADIATION DETECTORS, RADIOISOTOPES, REACTOR MATERIALS, REACTORS, SAFETY, SOLID HOMOGENEOUS REACTORS, SPONTANEOUS FISSION RADIOISOTOPES, THERMOCHEMICAL PROCESSES, TRANSURANIUM ELEMENTS, YEARS LIVING RADIOISOTOPES
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Kuijper, J. C.; Petrov, B. Y.; De Haas, J. B. M.; Bomboni, E.; Cerullo, N.; Lomonaco, G.; Mazzini, G.; Bernnat, W.; Meier, A.; Van Den Durpel, L.; Chauvet, V.; Cetnar, J.; Girardi, E.; Somers, J.; Abram, T.; Hesketh, K.; Mignanelli, M.; Jonnet, J.; Kloosterman, J. L.; Trakas, C.; Shihab, S.; Toury, G.; McEachern, D.; Venneri, F.; Zakova, J.; Millington, D.; Murgatroyd, J.; Werner, H.; Nabielek, H.; Verfondern, K.2008
AbstractAbstract
[en] The PUMA project, a Specific Targeted Research Project (STREP) of the European Union EURATOM 6. Framework Program, is mainly aimed at providing additional key elements for the utilisation and transmutation of plutonium and minor actinides (neptunium and americium) in contemporary and future (high temperature) gas-cooled reactor design, which are promising tools for improving the sustainability of the nuclear fuel cycle. PUMA would also contribute to the reduction of Pu and MA stockpiles and to the development of safe and sustainable reactors for CO2-free energy generation. The project runs from September 1, 2006 until August 31, 2009. PUMA also contributes to technological goals of the Generation IV International Forum. It contributes to developing and maintaining the competence in reactor technology in the EU and addresses European stakeholders on key issues for the future of nuclear energy in the EU. An overview is presented of the status of the project at mid-term. (authors)
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2008; 9 p; American Society of Mechanical Engineers - ASME; New York, NY (United States); HTR2008: 4. International Topical Meeting on High Temperature Reactor Technology; Washington, DC (United States); 28 Sep - 1 Oct 2008; ISBN 978-0-7918-3834-1; ; Country of input: France; 21 refs.
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Book
Literature Type
Conference
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