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Neutronic conceptual design of the ETRR-2 cold neutron source

  • M. Y. Khalil , M. K. Shaat and A. Y. Abdelfattah
Published/Copyright: May 5, 2013
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Kerntechnik
From the journal Kerntechnik Volume 70 Issue 3

Abstract

The conceptual neutronic design of the cold neutron source (CNS) for the Egyptian second research reactor (ETRR-2) was carried out using the MCNP code. A parametric analysis was also performed to choose the type and geometry of the moderator and the required CNS dimensions to maximize the cold neutron production. The moderator cell is a spherical annulus containing liquid hydrogen. The cold neutron gain and brightness are calculated together with the nuclear heat load of the CNS. The effects of void fraction in the moderator cell and the ortho:para ratios on cold neutron gain were calculated.

Kurzfassung

Der konzeptionelle Aufbau der kalten Neutronenquelle (CNS) des zweiten Ägyptischen Forschungsreaktors (ETRR-2) erfolgte mit Hilfe des MCNP Rechencodes. Eine parametrische Analyse wurde durchgeführt um Art und Geometrie des Moderators und der erforderlichen CNS Abmessungen zur Maximierung der Erzeugung kalter Neutronen auszuwählen. Die Moderatorzelle ist eine Ringkammer die flüssigen Wasserstoff enthält. Erzeugung und Flussdichte der kalten Neutronen wurden berechnet zusammen mit der Wärmeleistung der CNS. Die Einfluss des Dampfvolumenanteils in der Moderatorzelle und der Ortho-Para-Verhältnisse auf die Erzeugung kalter Neutronen wurde berechnet.

M. Y. Khalil, Nuclear Engineering Department, Alexandria University, Alexandria, Egypt and K. Shaat, A. Y. Abdelfattah, Nuclear Research Center, ETRR-2, EAEA, Cairo, Egypt

References

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Received: 2004-8-30
Published Online: 2013-05-05
Published in Print: 2005-05-01

© 2005, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries/Kurzfassungen
  5. Editorial
  6. 70 Volumes Kerntechnik
  7. Technical Contributions/Fachbeiträge
  8. Uncertainty and sensitivity analysis of void and power reactivity coefficients in an RBMK-1500 reactor core
  9. Theoretical studies on thermal stratification in a side heated cavity
  10. Measurement of the neutron fluence on the spallation source at Dubna
  11. Neutron reflection and leakage models for one-dimensional reactor computations
  12. Reactivity worth of the control rods at the ET-RR-2 reactor core
  13. Neutronic conceptual design of the ETRR-2 cold neutron source
  14. Criticality analyses of regions containing uranium in the earth history
  15. Semi-statistical mechanical fuel rod design
  16. Brennstabauslegung und Brennstabmodellierung – Teil 2
  17. The chemical separation of Eka-Hg from CERN W targets in view of recent relativistic calculations
  18. Letter to the Editor
  19. Comments on the question of the discovery of element 112 as early as 1971
https://doi.org/10.3139/124.100237

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries/Kurzfassungen
  5. Editorial
  6. 70 Volumes Kerntechnik
  7. Technical Contributions/Fachbeiträge
  8. Uncertainty and sensitivity analysis of void and power reactivity coefficients in an RBMK-1500 reactor core
  9. Theoretical studies on thermal stratification in a side heated cavity
  10. Measurement of the neutron fluence on the spallation source at Dubna
  11. Neutron reflection and leakage models for one-dimensional reactor computations
  12. Reactivity worth of the control rods at the ET-RR-2 reactor core
  13. Neutronic conceptual design of the ETRR-2 cold neutron source
  14. Criticality analyses of regions containing uranium in the earth history
  15. Semi-statistical mechanical fuel rod design
  16. Brennstabauslegung und Brennstabmodellierung – Teil 2
  17. The chemical separation of Eka-Hg from CERN W targets in view of recent relativistic calculations
  18. Letter to the Editor
  19. Comments on the question of the discovery of element 112 as early as 1971
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