Analysis and enhancements of the coolant velocity estimation method in PWR core

Author:

Kiss Sándor,Lipcsei Sándor

Funder

H2020 Euratom

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. Core Asymmetry Evaluation using Static Measurements and Neutron Noise Analysis;Adorján;Annals of Nuclear Energy,2000

2. Theoretical Investigation of the Local and Global Components of the Neutron-Noise Field in a Boiling Water Reactor;Behringer;Nuclear Science and Engineering,1977

3. Linear response of the Neutron Field to a Propagating Perturbation of Moderator Density (Two-Group Theory of Boiling Water Reactor Noise);Behringer;Nuclear Science and Engineering,1979

4. 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. Forshungszentrum Rossendorf, FYR-431: Final report on WP3, Wissenschaftlich-Technishe Beriche.

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

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