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Calculation of the energy deposition in the targets from C to U irradiated with intermediate energy protons

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Published/Copyright: May 2, 2013
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Kerntechnik
From the journal Kerntechnik Volume 69 Issue 3

Abstract

The energy deposition was calculated for the targets from carbon to uranium irradiated with intermediate energy protons with the help of different models incorporated in the MCNPX code package (Bertini, CEM and ISABEL) and with the help of the CASCADE/INPE code. The values obtained using the different models and codes are in a good agreement for all targets except uranium. The comparison with the available experimental data for the heat deposition for 0.8, 1.0 and 1.2 GeV protons has been performed. The good agreement is observed for copper, lead and bismuth target. The best result is obtained with the help of the ISABEL model. The systematic dependence of the heat deposition from atomic number of the target was investigated. The contribution of different particles and energy ranges in the heat deposition has been studied at the primary proton energies from 0.3 to 2.5 GeV.

Kurzfassung

Die Energiefreisetzung durch Bestrahlung mit Protonen mit Energien von 0.3 bis 2.5 GeV wurde systematisch berechnet mit den Codes MCNPX (Bertini, CEM und ISABEL Modelloptionen) und CASCADE/INPE. Die Ergebnisse dieser Rechnungen stimmen mit Ausnahme von Uran gut überein. Für die Energien 0.8, 1.0 und 1.2 GeV zeigen Vergleiche mit vorhandenen Experimenten gute Übereinstimmung, wobei die ISABEL Option des MCNPX Codes die besten Ergebnisse liefert. Der Beitrag der einzelnen Teilchen in den verschiedenen Energiebereichen auf die Energiefreisetzung wurde für primäre Proton-Energien von 0.3 bis 2.5 GeV analysiert.

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Received: 2003-10-6
Published Online: 2013-05-02
Published in Print: 2004-05-01

© 2004, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Improved Dancoff factors for cluster fuel bundles by the WIMSD code
  7. The impact of non-optimized operation of nuclear power plants on the nuclear fuel burn-up
  8. Experience with MTR fuel at the HOR reactor
  9. Comparison of two modern approaches for MBDA calculations of RBMK-type reactors
  10. Calculation of the energy deposition in the targets from C to U irradiated with intermediate energy protons
  11. U-Pb accelerator-driven sub-critical systems research at the proton beam of the JINR NUCLOTRON
  12. Steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor
  13. Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code
  14. Preliminary evaluation of the fixed and fluidized bed nuclear reactor concept using the IAEA-INPRO methodology
  15. Technical Notes/Technische Mitteilungen
  16. A clean nuclear blasting technique for the excavation of a new isthmus canal in Central America
https://doi.org/10.3139/124.100196

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Improved Dancoff factors for cluster fuel bundles by the WIMSD code
  7. The impact of non-optimized operation of nuclear power plants on the nuclear fuel burn-up
  8. Experience with MTR fuel at the HOR reactor
  9. Comparison of two modern approaches for MBDA calculations of RBMK-type reactors
  10. Calculation of the energy deposition in the targets from C to U irradiated with intermediate energy protons
  11. U-Pb accelerator-driven sub-critical systems research at the proton beam of the JINR NUCLOTRON
  12. Steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor
  13. Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code
  14. Preliminary evaluation of the fixed and fluidized bed nuclear reactor concept using the IAEA-INPRO methodology
  15. Technical Notes/Technische Mitteilungen
  16. A clean nuclear blasting technique for the excavation of a new isthmus canal in Central America
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