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Neutron Cross Section Sensitivity for Minor Actinide Transmutation in Energy Amplifier Systems
Uppsala University, Disciplinary Domain of Science and Technology, Physics, Department of Nuclear and Particle Physics.
2007 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 34, no 10, 824-835 p.Article in journal (Refereed) Published
Abstract [en]

The nuclear data sensitivity in 3D Monte Carlo burnup calculations of minor actinide transmutation in Energy Amplifier Systems is assessed. Ansaldo Nucleare's 80 MWth, Energy Amplifier Demonstration Facility (EADF) design serves as a technical and geometrical platform for the analysis. The accelerator-d riven EADF is a fast, subcritical system based on classical MOX-fuel technology and on molten lead-bismuth eutectic cooling. For Monte Carlo simulations, the state-of-the-art computer code package EA-MC, developed by C. Rubbia and his group at CERN, is utilised. The code offers treatment of both high-energy particle interactions and low-energy neutron transport with a sophisticated method based on a full Monte Carlo simulation, together with the option of employing different modern nuclear data libraries. In particular, the impact of nuclear data discrepancies on transmutation properties prediction with increasing exposure is examined. Monte Carlo simulation accelerator-driven systems transmutation burnup fast neutron spectrum minor actinides nuclear waste.

Place, publisher, year, edition, pages
2007. Vol. 34, no 10, 824-835 p.
National Category
Physical Sciences
URN: urn:nbn:se:uu:diva-94022DOI: 10.1016/j.anucene.2006.05.012ISI: 000250159400007OAI: oai:DiVA.org:uu-94022DiVA: diva2:167706
Available from: 2006-02-17 Created: 2006-02-17 Last updated: 2011-01-21Bibliographically approved
In thesis
1. Studies of Accelerator-Driven Systems for Transmutation of Nuclear Waste
Open this publication in new window or tab >>Studies of Accelerator-Driven Systems for Transmutation of Nuclear Waste
2006 (English)Doctoral thesis, comprehensive summary (Other academic)
Alternative title[sv]
Studier av acceleratordrivna system för transmutation av kärnavfall
Abstract [en]

Accelerator-driven systems for transmutation of nuclear waste have been suggested as a means for dealing with spent fuel components that pose potential radiological hazard for long periods of time. While not entirely removing the need for underground waste repositories, this nuclear waste incineration technology provides a viable method for reducing both waste volumes and storage times. Potentially, the time spans could be diminished from hundreds of thousand years to merely 1.000 years or even less. A central aspect for accelerator-driven systems design is the prediction of safety parameters and fuel economy. The simulations performed rely heavily on nuclear data and especially on the precision of the neutron cross section representations of essential nuclides over a wide energy range, from the thermal to the fast energy regime. In combination with a more demanding neutron flux distribution as compared with ordinary light-water reactors, the expanded nuclear data energy regime makes exploration of the cross section sensitivity for simulations of accelerator-driven systems a necessity. This fact was observed throughout the work and a significant portion of the study is devoted to investigations of nuclear data related effects. The computer code package EA-MC, based on 3-D Monte Carlo techniques, is the main computational tool employed for the analyses presented. Directly related to the development of the code is the extensive IAEA ADS Benchmark 3.2, and an account of the results of the benchmark exercises as implemented with EA-MC is given. CERN's Energy Amplifier prototype is studied from the perspectives of neutron source types, nuclear data sensitivity and transmutation. The commissioning of the n_TOF experiment, which is a neutron cross section measurement project at CERN, is also described.

Place, publisher, year, edition, pages
Uppsala: Acta Universitatis Upsaliensis, 2006. x+52 p.
Digital Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology, ISSN 1651-6214 ; 146
Nuclear physics, transmutation, accelerator-driven systems, Energy Amplifier, subcritical reactors, nuclear waste, Monte Carlo simulation, burnup, actinides, fission products, benchmark, nuclear data, neutron cross sections, sensitivity analysis, neutron source, spallation target, n_TOF experiment, neutron time-of-flight, cross section measurement, FLUKA, EA-MC, MCNP, MCNP-X, EADF, TRADE, Kärnfysik
National Category
Subatomic Physics
urn:nbn:se:uu:diva-6341 (URN)91-554-6462-9 (ISBN)
Public defence
2006-03-10, Polhemsalen, Ångströmlaboratoriet, Uppsala, 09:00
Available from: 2006-02-17 Created: 2006-02-17Bibliographically approved

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