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Anti-neutrino flux in a research reactor for non-proliferation application

  • S. Khakshournia und Sh. Foroughi
Veröffentlicht/Copyright: 20. Oktober 2017
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Kerntechnik
Aus der Zeitschrift Kerntechnik Band 82 Heft 5

Abstract

Owing to growing interest in the study of emitted antineutrinos from nuclear reactors to test the Atomic Energy Agency safeguards, antineutrino flux was studied in the Tehran Research Reactor (TRR) using ORIGEN code. According to our prediction, antineutrino rate was obtained 2.6 × 1017 (ν¯e/sec) in the core No. 57F of the TRR. Calculations indicated that evolution of antineutrino flux was very slow with time and the performed refueling had not an observable effect on antineutrino flux curve for a 5 MW reactor with the conventional refueling program. It is seen that for non-proliferation applications the measurement of the contribution of 239Pu to the fission using an antineutrino detector is not viable in the TRR.

Kurzfassung

Wegen des großen Interesses an der Untersuchung von frei werdenden Antineutrinos für Überwachungsmaßnahmen der Atomic Energy Agency wurde der Antineutrinofluss im Teheraner Forschungsreaktor (TRR) mit Hilfe des ORIGEN Rechencodes untersucht. Dabei wurde eine Antineutrinorate von 2.6 × 1017 (ν¯e/sec) im Kern des TRR berechnet. Die Berechnungen zeigen, dass die Entwicklung des Antineutrinoflusses sehr langsam vor sich ging und die durchgeführte Beladung keinen beobachtbaren Effekt auf den Antineutrinofluss hatte. Es zeigte sich, dass für Überwachungsmaßnahmen im Rahmen von Nichtverbreitungs-Anwendungen die Messung des Beitrags von 239Pu zur Spaltung mit Hilfe eines Antineutrinodetektors beim TRR nicht praktikabel ist.

* Corresponding author: E-mail:

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Received: 2017-03-31
Published Online: 2017-10-20
Published in Print: 2017-10-26

© 2017, Carl Hanser Verlag, München

Artikel in diesem Heft

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Modelling Human Resource Requirements for the Nuclear Industry in Europe
  7. Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
  8. The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant
  9. Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR
  10. Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5
  11. The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
  12. Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident
  13. Anti-neutrino flux in a research reactor for non-proliferation application
  14. Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
  15. Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach
  16. Internal and external hazards inside the containment in case of an emergency situation
  17. Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method
https://doi.org/10.3139/124.110798

Artikel in diesem Heft

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Modelling Human Resource Requirements for the Nuclear Industry in Europe
  7. Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
  8. The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant
  9. Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR
  10. Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5
  11. The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
  12. Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident
  13. Anti-neutrino flux in a research reactor for non-proliferation application
  14. Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
  15. Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach
  16. Internal and external hazards inside the containment in case of an emergency situation
  17. Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method
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