Analysis of propagating temperature perturbations in the primary circuit of PWRs

Author:

Kiss Sándor,Lipcsei Sándor

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference10 articles.

1. Core asymmetry evaluation using static measurements and neutron noise analysis;Adorján;Ann. Nucl. Energy,2000

2. Development of a method for measuring the moderator temperature coefficient by noise analysis and its experimental verification in ringhals-2;Demazière;Nucl. Sci. Eng.,2004

3. Elter, J., 2005, Experiment Summary Report: Experimental Investigation of Thermal Mixing Phenomena in a Six Loop VVER Type Reactor, The European project FLOMIX-R: Description of the experimental and numerical studies of flow distribution in reactor primary circuit. Final Report on WP3. Wissenschaftlich-Technishe Beriche, Forshungszentrum Rossendorf, FYR-431. pp. 87–103.

4. Measurement of average circulation period of temperature fluctuations in the coolant of VVER-440 reactors’ primary circuit;Kiss;Prog. Nucl. Energy,2014

5. Effect of the steam generator on temperature fluctuations of the primary circuit coolant in VVER-440 reactors;Kiss;Ann. Nucl. Energy,2014

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