Thermal study of the modular high-temperature gas-cooled reactor

Authors

  • Antonella Lombardi Costa Universidade Federal de Minas Gerais
  • Mario Cerrogrande Ramos Universidade Federal de Minas Gerais
  • Vitor Vasconcelos Araújo Silva
  • Claubia Pereira
  • Maria Auxiliadora Fortini Veloso

Keywords:

MHTGR, RELAP5-3D, Thermal Analysis

Abstract

The Modular High-Temperature Gas-Cooled Reactor (MHTGR) is an advanced power plant being a coupling between a modular helium cooled reactor and a gas turbine. The gas-cooled reactor types are of great interest due to their potential to provide high-temperature process heat in addition to their high thermal-to-electric power conversion efficiency and inherent safety features. The MHTGR is helium-cooled, graphite-moderated and uses Triso-coated fuel particles immersed in a cylindrical-shaped graphite matrix. The annular core and fuel blocks are based on the FSV (Fort Saint Vrain) reactor design.  In this work, a MHTGR model developed in the RELAP5-3D code is presented, as well as its verification for steady state calculations. The core simulations have been performed to three power values: 350, 450 and 600 MWth. The heat transfer along the blocks was investigated taking into account the diversion flow. The radial power distribution within the compact fuel was assumed to be uniform for the analysis. Radial and axial normalized power factors were specified for each axial segment in the heat structures that are coupled to the thermal hydraulic channels that shape the reactor core.  In the analyses, coolant and fuel temperatures, pressure drop and mass flow rate were verified at steady state conditions. The results were very close to the reference ones demonstrating that the developed model is capable to reproduce the MHTGR core in steady state operation.

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References

General Atomic, Gas Turbine-Modular Helium Reactor (GT-MHR) Conceptual Design Description Report. GA Project No. 7658. General Atomic, California, 1966.

TURNER, R. F. and NEYLAN, A. J., MHTGR Design and Development Status. GA PROJECT 7000, General Atomics, 1988.

YOON, S.J.et al. The Effects of Crossflow Gap and Axial Bypass Gap Distribution on the Flow Characteristics in Prismatic VHTR Core. Nuclear Engineering and Design, vol. 250, p. 465-479, 2012.

RAMOS, M. C. et al. Steady‐state thermal simulations of the liquid‐salt‐cooled high‐temperature reactor. International Journal of Energy Research, p. 1–10, 2017.

SCARI, M. E. et al., Thermal Hydraulic analysis and modeling of the HTTR using the RELAP5-3D. Journal of Nuclear Energy Science & Power Generation Technology, vol. 1, p. 1-6, 2017.

SCARI, M. E. et al., HTR steady state and transient thermal analyses. International Journal of Hydrogen Energy, vol. 41, p. 7192-7196, 2016.

INGERSOLL, D. T., Status of Physics and Safety Analyses for the Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR). ORNL/TM-2005/218. ORNL, Tennessee, 2005.

INGERSOLL, D. T., FORSBERG, C. W., MACDONALD, P. E., Trade Studies for the Liquid- Salt-Cooled Very High Temperature Reactor: Fiscal Year 2006 Progress Report. ORNL/TM-2006/140. ORNL, Tennessee, 2007.

U. S. DOE. Preliminary safety information document for the standard MHTGR. DOE/HTGR 86-024 Vol. 1. United States Department of Energy, 1986.

ORTENSI, J. et al., 2013 Prismatic Coupled Neutronics/Thermal Fluids Transient Benchmark of the MHTGR-350 MW Core Design: Benchmark Definition, OECD Nuclear Energy Agency, NEA/NSC/DOC DRAFT, 2013.

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Published

2022-10-29

How to Cite

Costa, A. L., Cerrogrande Ramos, M., Vasconcelos Araújo Silva , V. ., Pereira, C., & Auxiliadora Fortini Veloso, M. . (2022). Thermal study of the modular high-temperature gas-cooled reactor. Brazilian Journal of Radiation Sciences, 10(3A (Suppl.). Retrieved from https://bjrs.org.br/revista_33014/index.php/REVISTA/article/view/1879

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Section

INAC 2021_XXII ENFIR_VII_ENIN

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