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Publications
/ Journal article
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In target yields for EURISOL RIB production
D. Ene, S. Chabod, J.-C. David, D. Ridikas
The goal of this paper is the estimation of the in-target neutron-induced fission fragment productions using the most recent optimized design of the EURISOL converter-fission target assembly.
Submitted to EPJA.
EURISOL Desktop Assistant Toolkit\' (EDAT): A Modeling, Simulation and Visualization Support to the Preliminary Radiological Assessment of RIB Projects
D. Vamanu, B. Vamanu, V. Acasandrei, E. Maceika, A. Plukis
The paper describes an approach taken within EURISOL-DS project (European Isotope Separation On-Line Radioactive Ion Beam Facility) to a number of safety and radioprotection issues raised by the advent of radioactive ion beam facilities in the cutting edge area of particle accelerators. The ensuing solution emerged from a collaborative effort of the investigating team-in-charge, affiliated with ‘Horia Hulubei’ National Institute of Physics and Nuclear Engineering in Bucharest, with expert colleagues at the Physics Institute in Vilnius, and at CERN.
MODELING OF NEUTRON AND PHOTON TRANSPORT IN IRON AND CONCRETE RADIATION SHIELDS BY USING MONTE CARLO METHOD - VERSION 2
A. Zukauskaite, R. Plukiene A. Plukis, D. Ridikas
Particle accelerators and other high energy facilities produce penetrating ionizing radiation (neutrons and γ-rays) that must be shielded. The objective of this work was to model photon and neutron transport in various materials, usually used as shielding, such as concrete, iron or graphite. Monte Carlo method allows obtaining answers by simulating individual particles and recording some aspects of their average behavior. In this work several nuclear experiments were modeled: AVF 65 – γ-ray beams (1-10 MeV), HIMAC and ISIS-800 – high energy neutrons (20-800 MeV) transport in iron and concrete. The results were then compared with experimental data.
Radiation protection aspects of the EURISOL Multi-MW target shielding
D. Ene, J.-C. David, D. Doré, B. Rapp, D. Ridikas
This paper which will be submitted to Annals in Nuclear Energy is focused on the approach used to assess the radiological characterisation and to support waste analysis for the multi-MW power target shielding being the most challenging both in terms of technological and safety issues.
Characterization of a highly-efficient aerosol filtration system
P.G. Thirolf, D. Habs, A.~Kohlhund, F.~Nebel, J.B.~Neumayr, R.~Stoepler
LMU Munich and Maier-Leibni...
Contribution to the annual report (2007) of the Maier-Leibnitz Laboratory, Garching
Localization of volatile isotopes on a cryotrap
P.G. Thirolf, M. Gross, D. Habs, A. Kohlhund, F. Nebel, J.B. Neumayr, R. Stoepler, J. Szerypo
Article to be submitted to Nucl. Instr. Meth. B for
the Proceedings of the EMIS 2007 Conference, Deauville/France.
Ref. Nucl. Instr. Meth. B 266(2008) 4505.
MODELING OF NEUTRON AND PHOTON TRANSPORT IN IRON AND CONCRETE RADIATION SHIELDS BY USING MONTE CARLO METHOD
A. Zukauskaite, R. Plukiene A. Plukis, D. Ridikas
Particle accelerators and other high energy facilities produce penetrating ionizing radiation (neutrons and γ-rays) that must be shielded. The objective of this work was to model photon and neutron transport in various materials, usually used as shielding, such as concrete, iron or graphite. Monte Carlo method allows obtaining answers by simulating individual particles and recording some aspects of their average behavior. In this work several nuclear experiments were modeled: AVF 65 – γ-ray beams (1-10 MeV), HIMAC and ISIS-800 – high energy neutrons (20-800 MeV) transport in iron and concrete. The results were then compared with experimental data.
Localisation of volatile isotopes on cryotraps
J.B. Neumayr, M. Gross, D. Habs, A. Kohlhund, H.J. Maier, P. Maier-Komor, F. Nebel, R. Stoepler, J. ...
Contribution for the Annual Report 2006 of the Maier-Leibnitz-Laboratory, Garching
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