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Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code

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

Abstract

The MCNP computer Code is used to model the ETRR-2 research reactor. A computer program was designed to evaluate the axial burn-up of the fuel elements. The excess reactivity of the reactor core is calculated for different core configurations and compared with the existing measurements. The thermal flux is also calculated and compared with measurements. Several factors that affect the safety of the reactor such as power peak and the effect of control rod insertion on the reactor power and flux were studied and analysed. The agreement between the MCNP results and the experimentally determined values is good.

Kurzfassung

Zur Modellierung des ETRR-2 Forschungsreaktors wurde der MCNP Computercode verwendet. Es wurde ein Computerprogramm entwicklet zur Auswertung des axialen Abbrandes der Brennelemente. Die Überschussreaktivität wurde für verschiedene Kernkonfigurationen berechnet und mit den vorhandenen Messungen verglichen. Der thermische Neutronenfluss wird ebenfalls berechnet und mit Messungen verglichen. Verschiedene Faktoren, die die Sicherheit des Reaktors beeinflussen wie z. B. die Leistungsspitze oder der Einfluss der Leistungsregelung auf die Reaktorleistung und den Neutronenfluss wurden analysiert. Die Übereinstimmung zwischen den MCNP Ergebnissen und den experimentell bestimmten Werten ist gut.

References

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Received: 2003-12-3
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/10.3139/124.100199

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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