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Showing 1-11 of 11 results

  1. Main Results of the Trial Test of a Closed Circuit with Natural Circulation of a Light-Water Coolant under Supercritical Pressure

    Abstract

    Main results are presented of the trial tests of a closed loop with natural circulation (NC) of a light-water coolant under supercritical...

    A. A. Sedov, P. S. Polyakov, ... S. S. Simonov in Thermal Engineering
    Article 12 March 2023

  2. The Concept of a Nuclear Power Unit on the Basis of a Low-Power Multipurpose Test Research Reactor with Supercritical Light-Water Coolant

    Abstract

    Herein is presented a preliminary concept of a nuclear power installation (NPI) based on a low-power multipurpose test research reactor with...

    A. A. Sedov, V. Yu. Blandinskii, ... A. A. Frolov in Thermal Engineering
    Article 19 May 2023

  3. Estimating the Steam Quality in Power-Generating Boilers from Electrical Conductivity and pH Measurements

    Abstract—

    The quality of steam produced by boilers is strictly standardized and must be maintained whatever the quality of makeup water and whatever...

    A. B. Larin, B. M. Larin, M. P. Savinov in Thermal Engineering
    Article 17 May 2021

  4. Prospects for development of an innovative water-cooled nuclear reactor for supercritical parameters of coolant

    The state of nuclear power engineering as of February 1, 2014 and the accomplished elaborations of a supercritical-pressure water-cooled reactor are...

    S. G. Kalyakin, P. L. Kirillov, ... A. N. Churkin in Thermal Engineering
    Article 19 July 2014

  5. Prospects for development of nuclear power stations equipped with VVER reactors

    The prospects for further development in Russia of nuclear stations equipped with water-cooled water-moderated reactors are considered.

    Yu. M. Semchenkov, V. A. Sidorenko in Thermal Engineering
    Article 20 May 2011

  7. MIF-SKD computation code for thermohydraulic design of a reactor core cooled by supercritical-pressure water

    Presented here is the MIF-SKD computation code for channel-by-channel thermohydraulic calculations of fuel-rod assemblies cooled by...

    G. P. Bogoslovskaya, A. A. Karpenko, ... A. P. Sorokin in Thermal Engineering
    Article 12 March 2009

  8. Supercritical water cooled reactors

    The main advantages of implementation of water-moderated water-cooled power reactors with supercritical parameters in power engineering are shown.

    P. L. Kirillov in Thermal Engineering
    Article 16 May 2008

  9. Problems and prospects of new generation light-water reactors at supercritical pressure

    Basic problems in neutron physics, structural materials of fuel rods, and assemblies (FA) for a new generation light-water reactors with...

    Yu. M. Semchenkov, A. S. Dukhovenskii, ... A. V. Chibinyaev in Thermal Engineering
    Article 16 May 2008

  10. Target view of the strategy of the Russian power engineering development during the period to 2030

    Yu. A. Zeigarnik, V. M. Maslennikov, ... I. S. Shevchenko in Thermal Engineering
    Article 01 November 2007

  11. The use of supercritical parameters of a coolant—A promising path to development of nuclear power plant water-cooled reactors in the 21st century

    A modern concept of the development of water-cooled reactors of nuclear power plants (NPPs) is considered. Data on the design of NPPs with...

    B. A. Gabaraev, V. N. SMolin, S. L. Solov’ev in Thermal Engineering
    Article 01 September 2006
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