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Background <p>The main conditions for the safe operation of fuel assemblies (FAs) in the core of the research IVV-2M heterogeneous water-water reactor of a&#xa0;pool type involve the absence of surface boiling on the fuel element cladding, including under the layer of deposits. The values of the coolant flow rate through the inter-fuel gaps can be used to predict the coolant temperature at the outlet of the FA over the campaign and justify the operating limit settings.</p> Aim <p>To determine the functional dependence of the coolant flow rate through FAs on their burnup depth and residence time in the core based on the results of measuring the coolant flow rate through individual FAs.</p> Materials and methods <p>A&#xa0;FLUXUS ADM 7407 ultrasonic device was used for mobile monitoring of the coolant flow rate through the inter-fuel gaps of FAs in the IVV-2M nuclear research facility; the device was developed and manufactured at the N.A.&#xa0;Dollezhal Research and Design Institute of Power Engineering JSC. The measurements were carried out under a&#xa0;layer of water; the flowmeter was installed directly on the FA. The measurement methodology and derived analytical dependence of the flow rate on the pressure drop in the core are presented in the article “Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part&#xa0;1”.</p> Results <p>Analytical dependencies of the flow rate on the burnup depth and residence time of the FA in the core are derived using the data from measurements of the coolant flow rate in the IVV-2M FAs during several years of reactor operation.</p> Conclusion <p>The obtained dependencies can be used to estimate the coolant flow rate through the inter-fuel gaps of the FA without conducting direct measurements, as well as to more accurately determine the temperature on the fuel element cladding, thereby increasing the operational safety of the nuclear research facility. The measurements should be continued on operating reactor for accumulating statistical data to clarify the dependencies and reduce errors.</p>

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Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 2

  • 期刊论文

  • 发表日期：

    2025年9月1日

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  • I. M. Russkikh,
  • E. N. Seleznev,
  • A. A. Zyryanova,
  • Yu. V. Volchikhina,
  • N. M. Aristov,
  • N. S. Kalashnikov,
  • A. V. Goryachikh,
  • O. A. Kravtsova,
  • O. L. Tashlykov

摘要

Background

The main conditions for the safe operation of fuel assemblies (FAs) in the core of the research IVV-2M heterogeneous water-water reactor of a pool type involve the absence of surface boiling on the fuel element cladding, including under the layer of deposits. The values of the coolant flow rate through the inter-fuel gaps can be used to predict the coolant temperature at the outlet of the FA over the campaign and justify the operating limit settings.

Aim

To determine the functional dependence of the coolant flow rate through FAs on their burnup depth and residence time in the core based on the results of measuring the coolant flow rate through individual FAs.

Materials and methods

A FLUXUS ADM 7407 ultrasonic device was used for mobile monitoring of the coolant flow rate through the inter-fuel gaps of FAs in the IVV-2M nuclear research facility; the device was developed and manufactured at the N.A. Dollezhal Research and Design Institute of Power Engineering JSC. The measurements were carried out under a layer of water; the flowmeter was installed directly on the FA. The measurement methodology and derived analytical dependence of the flow rate on the pressure drop in the core are presented in the article “Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 1”.

Results

Analytical dependencies of the flow rate on the burnup depth and residence time of the FA in the core are derived using the data from measurements of the coolant flow rate in the IVV-2M FAs during several years of reactor operation.

Conclusion

The obtained dependencies can be used to estimate the coolant flow rate through the inter-fuel gaps of the FA without conducting direct measurements, as well as to more accurately determine the temperature on the fuel element cladding, thereby increasing the operational safety of the nuclear research facility. The measurements should be continued on operating reactor for accumulating statistical data to clarify the dependencies and reduce errors.