U-Pb accelerator-driven sub-critical systems research at the proton beam of the JINR NUCLOTRON
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V. S. Barashenkov
Abstract
Neutron spectra, yields and energies of particles generated by a uranium electro-nuclear set-up which is now used in Dubna for transmutation research of various isotopes with a proton beam of an energy of 1–2 GeV, were analyzed by means of mathematical modelling based on the Monte Carlo code CASCADE. The influence of space dispersion on the proton beam and its possible deviation from the center of a lead target is investigated. It is shown that the polyethylene radiation shielding that is being used now, does not protect the measuring room from neutrons and γ-rays.
Kurzfassung
Neutronenspektren, Ausbeuten und Energien von Teilchen, die mit Hilfe einer elektronuklearen Anordnung wie sie zur Zeit in Dubna für die Transmutationsforschung an verschiedenen Isotopen mit Protonenstahlen einer Eergie von 1–2 GeV verwendet wird wurden mit mathematischen Modellen auf der Basis des Monte Carlo Codes CASCADE analysiert. Der Einfluss der räumlichen Dispersion auf den Protonenstrahl und seine mögliche Ablenkung vom Zentrum eines Bleitargets wurde untersucht. Es wird gezeigt, dass die jetzt verwendete Abschirmung aus Polyäthylen den Messraum nicht vor Neutronen und Gammastrahlen schützt.
References
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© 2004, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved Dancoff factors for cluster fuel bundles by the WIMSD code
- The impact of non-optimized operation of nuclear power plants on the nuclear fuel burn-up
- Experience with MTR fuel at the HOR reactor
- Comparison of two modern approaches for MBDA calculations of RBMK-type reactors
- Calculation of the energy deposition in the targets from C to U irradiated with intermediate energy protons
- U-Pb accelerator-driven sub-critical systems research at the proton beam of the JINR NUCLOTRON
- Steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor
- Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code
- Preliminary evaluation of the fixed and fluidized bed nuclear reactor concept using the IAEA-INPRO methodology
- Technical Notes/Technische Mitteilungen
- A clean nuclear blasting technique for the excavation of a new isthmus canal in Central America
