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Evaluation of advanced displacement cross-sections for the major EUROFER constituents based on an atomistic modelling approach

  • A. Yu. Konobeyev , U. Fischer and P. E. Pereslavtsev
Published/Copyright: March 21, 2015
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Kerntechnik
From the journal Kerntechnik Volume 80 Issue 1

Abstract

The displacement cross-sections were evaluated for main components of EUROFER at the energies of primary neutrons up to 150 MeV. The number of primary defects was calculated using an advanced binary collision approximation model applying results of molecular dynamics simulations. The cross-sections obtained were processed into ENDF and ACE formatted data and tested using the MCNP code.

Kurzfassung

Verlagerungsquerschnitte für Grundkomponenten von EUROFER wurden für Neutronenenergien bis 150 MeV ausgewertet. Die Anzahl der stabilen Defekte wurde mit Hilfe eines weiterentwickelten binären Stoßapproximation-Modells mit einer nachfolgenden Korrektur auf der Basis der Simulationen der molekularen Dynamik berechnet. Die berechneten Wirkungsquerschnitte wurden in ENDF- und ACE-Daten umgewandelt und mit Hilfe von MCNP getestet.

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References

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Received: 2014-12-05
Published Online: 2015-03-21
Published in Print: 2015-03-17

© 2015, Carl Hanser Verlag, München

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  3. Summaries/Kurzfassungen
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https://doi.org/10.3139/124.110483

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Evaluation of advanced displacement cross-sections for the major EUROFER constituents based on an atomistic modelling approach
  7. Tarapur atomic power station: analysis of station blackout scenario
  8. Estimating steady state and transient characteristics of molten salt natural circulation loop using CFD
  9. Thermal hydraulic analysis of ETRR-2 using RELAP5 code
  10. Transient performance during stopping the research reactor primary loop pump
  11. Neutronic performance calculations with alternative fluids in a hybrid reactor by using the Monte Carlo method
  12. A study on the criticality of modified neutron transport equation by using alternative scattering phase functions
  13. Production cross–section calculations of medical 32P, 117Sn, 153Sm and 186,188Re radionuclides used in bone pain palliation treatment
  14. Study on carbonated hydroxyapatite as a thermoluminescence dosimeter
  15. Social impact theory based modeling for security analysis in the nuclear fuel cycle
  16. Analysis of a homogenous and heterogeneous stylized half core of a CANDU reactor
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