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Development of the Physical and Technical Foundations of the Technology of High-Temperature Gas-Cooled Reactor Systems

  • P. A. Fomichenko,
  • A. V. Grol,
  • V. A. Nevinitsa,
  • A. A. Sedov,
  • A. L. Balanin,
  • V. F. Boyarinov,
  • M. A. Agulnik,
  • V. V. Degtyarev,
  • A. S. Ivanov,
  • Yu. A. Veselkin,
  • D. B. Stepennov,
  • A. A. Bobrov

摘要

Abstract

The results of a part of works carried out by the NRC Kurchatov Institute in the development of the physical and technical foundations of the technology of high-temperature gas-cooled reactor (HTGR) systems are presented. Integral components of the development of the physical and technical foundations of the HTGR technology are the improvement of methodology and software for calculations to justify the nuclear and physical part of the project and experimental studies, such as the study of neutronic characteristics of reactors of this type on a critical facility, the study of tightness of fuel samples, and materials science studies of samples in fuel quality control procedures. Maintaining the HTGR knowledge base makes it possible to consolidate the accumulated experience and identify individual critical technologies and is also used in the preparation and implementation of technological development plans aimed at obtaining missing design data.