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CANDU fuel elements behaviour in the load following tests

  • G. Horhoianu and S. Palleck
Published/Copyright: April 19, 2013
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Kerntechnik
From the journal Kerntechnik Volume 76 Issue 4

Abstract

Two load following (LF) tests on CANDU type fuel elements were performed in TRIGA Research Reactor of INR Pitesti. In the first LF test the 78R fuel element has successfully experienced 367 power cycles, mostly between 23 and 56 kW/m average linear power. In the second LF test, the fuel element withstood 200 power cycles from 27 to 54 kW/m average linear power as well as additional ramps due to reactor trips and restarts during test period. New LF tests are planed to be performed in order to establish the limits and capabilities for CANDU fuel in LF conditions. This paper presents the results of the LF tests performed in TRIGA Research Reactor and their relation to CANDU fuel performance in LF conditions.

Kurzfassung

Zwei Tests wurden nach der Beladung (LF) mit Brennelementen vom CANDU-Typ am TRIGA Forschungsreaktor des INR Pitesti durchgeführt. Beim ersten LF Test hatte das 78R Brennelement erfolgreich 367 Leistungszyklen meist bei durchschnittlicher Leistung zwischen 23 and 56 kW/m absolviert. Beim zweiten LF Test widerstand das Brennelement 200 Leistungszyklen zwischen 27 and 54 kW/m durchschnittlicher linearer Leistung, sowie zusätzlichen Anstiegen aufgrund von Reaktor Schnellabschaltungen und Neustarts während der Testperiode. Neue LF Tests sind geplant, um Grenzen und Leistungsvermögen für CANDU Brennelemente unter LF Bedingungen zu bestimmen.

References

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Received: 2010-11-26
Published Online: 2013-04-19
Published in Print: 2011-08-01

© 2011, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Stress analyses for reactor pressure vessels by the example of a product line '69 Boiling Water Reactor
  7. Multiple condensation induced water hammer events, experiments and theoretical investigations
  8. Simulation of load following mode of operation for a natural circulation pressure tube type BWR
  9. CANDU fuel elements behaviour in the load following tests
  10. Local heat transfer coefficient near the spacer grids
  11. Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module
  12. Investigations of bi-directional flow behaviour in presence of a large vertical opening in a fire compartment
  13. CANDU reactors with reactor grade plutonium/thorium carbide fuel
  14. Novel method to produce 109Cd via proton irradiation of electroplated silver on a gold-coated copper backing
  15. Technical Notes/Technische Mitteilungen
  16. Atmospheric dispersion of accidental release of radioactive gases from high enriched and low enriched fuel of Miniature Neutron Source Reactors (MNSR)
  17. Fuel burnup of modified fuel assembly configurations for a small medical reactor
  18. Determination of natural uranium, thorium and radium isotopes in water and soil samples by alpha spectroscopy
https://doi.org/10.3139/124.110156

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Stress analyses for reactor pressure vessels by the example of a product line '69 Boiling Water Reactor
  7. Multiple condensation induced water hammer events, experiments and theoretical investigations
  8. Simulation of load following mode of operation for a natural circulation pressure tube type BWR
  9. CANDU fuel elements behaviour in the load following tests
  10. Local heat transfer coefficient near the spacer grids
  11. Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module
  12. Investigations of bi-directional flow behaviour in presence of a large vertical opening in a fire compartment
  13. CANDU reactors with reactor grade plutonium/thorium carbide fuel
  14. Novel method to produce 109Cd via proton irradiation of electroplated silver on a gold-coated copper backing
  15. Technical Notes/Technische Mitteilungen
  16. Atmospheric dispersion of accidental release of radioactive gases from high enriched and low enriched fuel of Miniature Neutron Source Reactors (MNSR)
  17. Fuel burnup of modified fuel assembly configurations for a small medical reactor
  18. Determination of natural uranium, thorium and radium isotopes in water and soil samples by alpha spectroscopy
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