Skip to main content

Advertisement

Log in

Substantiation of the parameters and layout solutions for an energy conversion unit with a gas-turbine cycle in a nuclear power plant with HTGR

  • Published:
Atomic Energy Aims and scope

Abstract

Light is shed on questions concerning the application of a direct closed gas-turbine cycle for generating electricity in a nuclear power plant with HTGR. This makes it possible to use such reactor systems for generating electricity and(or) producing hydrogen from water and combine high electricity-generation efficiency of 47–50% with high safety. It is shown that it is advantageous to use a recovery gas cycle with recovery efficiency of at least 95% and intermediate cooling of helium in a compressor. The choice of the configuration of the reactor system is substantiated. The heat-exchange equipment of the gas-turbine cycle should have unique characteristics when placed in vessels with limited size and for operation at high temperatures (up to 600°C) and with a large pressure drop (up to 5 MPa). Approaches to solving the problems studied are elucidated on the basis of a modular helium reactor with a GT-MGR gas turbine.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Similar content being viewed by others

REFERENCES

  1. G. Melese and R. Katz, “Thermal and flow design of helium-cooled reactors,” in: Nuclear Science and Technology Monograph Ser. American Nuclear Society, Illinois, USA (1984), pp. 250–292.

  2. V. F. Golovko, I. V. Dmitrieva, N. G. Kodochigov, and N. G. Kuzavkov, “Features of adapting gas turbine cycle and heat exchangers for HTGRS,” in: Proceedings of the Technical Committee Meeting, Palo Alto, CA, November 14–16, 2000, IAEA-TECDOC-1238 (2001), pp. 63–74.

  3. A. I. Kiryushin, N. G. Kodochigov, N. G. Kuzavkov, et al., “Project of the GT-MHR high-temperature helium reactor with gas turbine,” Nucl. Eng. Design, 173, 119–129 (1997).

    Article  CAS  Google Scholar 

  4. “Current status and future development of modular high-temperature gas-cooled reactor technology. Chapter 3: Review of the Pebble Bed Modular Reactor (PBMR) Plant,” in: IAEA-TECDOC-1198 (2001), pp. 19–68.

  5. É. A. Manushin, V. S. Beknev, M. I. Osipov, and I. G. Surovtsev, Nculear Gas-Turbine and Combined Systems, Énergoatomizdat, Moscow (1993).

    Google Scholar 

  6. V. Traupel, Thermal Turbomachines (Steam and Gas Turbines, Compressors) [Russian translation], Gosénergoizdat, Moscow (1963), Vol. 2: Regulation, Strength, and Dynamics Problems, pp. 73–178.

    Google Scholar 

Download references

Authors

Additional information

I. I. Afrikantov Special Office Design for Machine Engineering.

__________

Translated from Atomnaya Énergiya, Vol. 98, No. 1, pp. 24–36, January, 2005.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Vasyaev, A.V., Golovko, V.F., Dmitrieva, I.V. et al. Substantiation of the parameters and layout solutions for an energy conversion unit with a gas-turbine cycle in a nuclear power plant with HTGR. At Energy 98, 21–31 (2005). https://doi.org/10.1007/s10512-005-0164-z

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-005-0164-z

Keywords

Navigation