Skip to main content

Components of the Helium Cycle

  • Chapter
  • First Online:
Modular High-temperature Gas-cooled Reactor Power Plant
  • 1108 Accesses

Abstract

The primary helium cycle of a steam-generating HTR mainly contains the hot gas duct, the steam generator, the helium circulator, and the cold gas duct together with the nuclear reactor as heat source. Additionally, a gas purification plant and helium auxiliary systems have to be considered as further helium systems. Different helium cycles have been operated with success over many years. The helium technology with all important aspects, like heat transfer, pressure losses, tightness of systems, friction, wear, and corrosion by impurities, is known today, and adequate solutions are available. In this chapter, the main components are discussed in some detail. The hot gas duct can be realized as coaxial system with low-temperature losses and small pressure drops; the insulations and liner system for longtime operation are available. Suited high-temperature alloys for ducting the hot gas and for the tubes of the steam generator allow a design for the whole planned lifetime of the components. Aspects of thermo-hydraulic design and of the mechanical analysis of steam generators show that especially helical-type heat exchangers can be designed for the production of hot steam with high safety factors. Special aspects of design and operation and existing experiences with these components are described in this chapter too and show that solutions for all questions are developed. The circulators, which are necessary to compensate the pressure losses in the helium cycle, can be realized following different principles of design. For modular HTR, one-stage compressors of the radial type with electrical drive have a broad basis of experience and promise advantages to realize sufficient large units. One important aspect of helium cycles is to establish a suited helium atmosphere during operation. The content of impurities has to be limited to protect the graphitic structures of the fuel elements and the core internals against too high corrosion. For this purpose, helium circuits are connected to a gas purification plant, which reduces the content of impurities and of dust. In older designs, a removal of radioactive substance was foreseen too; however, this is not necessary today, if the very dense TRISO-coated particles are applied. Different auxiliary helium systems, like supply system for sealing gas for circulators, helium supply for the fuel handling systems, or a helium storage, are necessary for the operation of an HTR plant. Helium circuits for decay heat removal in some plants and designs were a further system of interest. The conditions of design are similar to those of the steam generator/helium circulator loop. The helium cycle needs different measurement installations for temperature, pressure and mass flow and the gas quality. Especially, the measurement of the water content in the helium has to be carried out carefully, because this measurement is safety relevant to detect water ingress accidents early.

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

Access this chapter

Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 299.00
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 379.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info
Hardcover Book
USD 379.99
Price excludes VAT (USA)
  • Durable hardcover edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

References

  1. Zhang. Z., et al, Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM, Nuclear Engineering and Design, 236, 2006

    Article  Google Scholar 

  2. Special Issue: A technology roadmap for Generation IV, Nuclear Energy Systems, issued by the US-DOE Nuclear Energy Research, Advisory Committee and the Generation IV International Forum, Dec. 2002

    Google Scholar 

  3. Poulter D., The design of gas-cooled graphite –moderated reactors, London Oxford University Press, 1963

    Google Scholar 

  4. Schulten R. and Trauger D., Gas-cooled reactors, Trans. Am. Nucl. Soc., 24, 1976

    Google Scholar 

  5. AVR experimental high-temperature reactor – 21 years of successful operation for a future energy technology, VDI-Verlag, 1990

    Google Scholar 

  6. Melese G. and Katz R., Thermal and flow design of helium-cooled reactors, American Nuclear Society, La Grange, Illinois, USA, 1984

    Google Scholar 

  7. Bedenig D., Gas-cooled high-temperature reactors, Verlag Karl Thiemig, München, 1972

    Google Scholar 

  8. Kugeler K. and Schulten R., High-temperature reactor technology, Springer Verlag, Berlin, Heidelberg, New York, London, Paris, Tokyo, Hongkong

    Google Scholar 

  9. Thermal insulations for gas-cooled reactors, in: Modern Power Station Practice: Nuclear Power Generation, Vol. 7, Pergamon Press, Oxford, New York, Seoul, Tokyo, 1992

    Google Scholar 

  10. Nickel H., Schubert F., Schuster H., Evaluation of alloys for advanced high-temperature reactor systems, Nuclear Engineering and Design 78, 1984, Nickel H., Schubert F., Schuster H., Very high temperature design criteria for nuclear heat exchanger in advanced high temperature reactor, Nuclear Engineering and Design 94, 1986, Nickel H., Schubert F., Schuster H., Status and development of the German materials program for the HTGR, IAEA Meeting, Jülich, Oct. 1986, Kurasa Y., et al., Evaluation of long-term creep properties of hastelloy XR in simulated high-temperature gas-cooled reactor helium, 3rd JAERI Symp. Oarai 1996 (Proc. JAERI-Conf. 96-010, 1996)

    Google Scholar 

  11. Siemens/Interatom, Chapter: hot gas duct, in: Sicherheitsbericht zur Modul HTR-Anlage, 1985

    Google Scholar 

  12. Bröckerhoff P., Test insulations for the hot gas ducts of the HHT plant, JŰL-1334, 1976

    Google Scholar 

  13. Bröckerhoff P. and Scholz F., Insulation behavior of dense fiber insulation systems at high-temperatures and pressures, Verfahrrenstechnik, 11, Nr. 4, 1977

    Google Scholar 

  14. HTR components, Status of development in the field of components which duct hot gases and transfer heat, Schriftenreihe “Energiepolitik in Nordrhein-Westfalen”, Bd. 16-1, 16-2, 1984

    Google Scholar 

  15. Noack G. and Weisskopf H., The high-temperature helium experimental facility (HHV): concept and description of plant, JŰL-1403, 1977

    Google Scholar 

  16. Bröckerhoff P., Insulation systems for the hot gas ducts of high-temperature reactors and their behavior at high pressures and temperatures, Journal of Non-Equilibrium Thermodynamics, Vol. 3, 1978

    Google Scholar 

  17. Furber B. N. and Sheppard M. A., Liner insulation for gas-cooled reactors – 21 years of development, Proceedings of the Conference “Gas-Cooled Reactors Today”, Vol. 1, British Nuclear Energy Society (BNES), 1982

    Google Scholar 

  18. Hishida M., Tanaka I., Shimomura H. and Sanokawa K., Construction and performance test of helium engineering demonstration loop (HEN-DEL)for VHTR, Specialists Meeting on Heat Exchanging Components of Gas-Cooled Reactors, International Atomic Energy Agency, IEGGCR-9, paper No. 29, 1984

    Google Scholar 

  19. Stehle H. and Klas E., Status of the development of hot gas duct for HTRs, Specialists Meeting on Heat Exchanging Components of Gas-Cooled Reactors, International Atomic Energy Agency, IEGGCR-9, paper No. 25, 1984

    Google Scholar 

  20. Klas E. and Bröckerhoff P., Experimental analysis on fibre insulation for the primary duct of an HTR plant, Jahrestagung Kerntechnik, 1984

    Google Scholar 

  21. Jansing W. and Teubner H., The high-temperature experimental facility KVK – Experience from 20000 hours of operation, Jahrstagung Kerntechnik, Germany, 1990

    Google Scholar 

  22. Bröckerhoff P., Research on thermal insulation for hot gas ducts, Specialists Meeting on Heat Exchanging Components of Gas-Cooled Reactors, International Atomic Energy Agency, IEGGCR-9, paper No. 27, 1984

    Google Scholar 

  23. Bröckerhoff P., Singh J., Schmitt H., Knaul J., Hiltgen H. and Stausebach D., Status of design and testing of hot gas ducts, Nuclear engineering and Design, No. 78, 1984

    Article  Google Scholar 

  24. Weisbrodt I. A., Summary report on technical experiences from high-temperature helium turbo machinery testing in Germany, IAEA, TEC DOC 899, 1996

    Google Scholar 

  25. Dumm K., Klas E. and Stausebach D., Development of hot gas ducts for high-temperature reactors in the temperature region till 950 °C, 3R International, 24. Jg., Heft 9, 1985

    Google Scholar 

  26. Bröckerhoff P., Hot gas insulations, JŰL-3911, Oct. 2001

    Google Scholar 

  27. Huang Z. Y. et al, Design and experiment of hot gas duct for HTR-10, Nuclear Engineering and Design, 218, 2002

    Article  Google Scholar 

  28. Schöning J., On the questions of material pairing under the specific conditions of high-temperature reactors, Diss. RWTH Aachen, March 1981

    Google Scholar 

  29. Quade R. N., Hunt P. S. and Schützendübel W. G., The design of the Fort St. Vrain steam generators, Nuclear Engineering and Design, 26, 1974

    Article  Google Scholar 

  30. Rosenbaum W., The steam generators for the nuclear power plant Schmelhausen THTR 300 MWel, EVT Register, 27, 1974

    Google Scholar 

  31. Bachmann U., Steam generators for high-temperature reactors – effects of design on the systems, Technische Rundschau Sulzer, Sonderheft Nuclex, 1975

    Google Scholar 

  32. Gilli P. V., Edler A., Halozan H. and Schaub P., Aspects of heat transfer, pressure drop and flow stability in thermal high stressed steam generator tubes, VGB Kraftwerkstechnik, 55, Nr. 9, 1975

    Google Scholar 

  33. Fricker H. W., Design and manufacturing experience for German Thorium high-temperature reactor 300 MWel steam generator, Nuclear Technology, Vol. 28, March 1976

    Google Scholar 

  34. Burgsmüller P., Fabrication experiments for large helix heat exchangers, Sulzer Technical Review, Nuclex 1978

    Google Scholar 

  35. Carosella D. P., Steam generator thermal performance model verification by use of Fort St. Vrain nuclear generation station test data, The American Society of Mechanical Engineers, 1979

    Google Scholar 

  36. Burgsmüller P. and Sarlos G., Steam generators and heat exchangers for gas-cooled reactors, Meeting of the IAEA, Minsk, 1981

    Google Scholar 

  37. NN. Siemens/Interatom, Concept of steam generator of HTR-Modul, Sicherheitsbericht des HTR Modul, Nov. 1981

    Google Scholar 

  38. Mondry M. and Singh J., Thermodynamic analysis for the AVR steam generator at part load, KFA-Report, Aug. 1984

    Google Scholar 

  39. Rizhu L. and Huaiming J., Structural design and two phase flow stability test for the steam generator of HTR-10, Nuclear Engineering and Design, 218, 2002

    Article  Google Scholar 

  40. Special issue, Project information of the THTR project, HRB, till 1987

    Google Scholar 

  41. Schmitz P., Design possibilities of helium heated steam generators for high-temperature reactors, Diss. RWTH Aachen, Jülich-1785, May 1982

    Google Scholar 

  42. Ziermann, Ivens G., Chapter: Steam generator and valves of steam generator, in: Final Report on the Power Operation of the AVR Experimental Nuclear Power Plant, JŰL-3448, Oct. 1997

    Google Scholar 

  43. Esch M., Knoche D., Hurtato A. and Tietsch W., Layout of helium-steam generators for high-temperature reactors for the production of process steam for industrial steam processes, Jahrestagung Kerntechnik (Germany), 2010

    Google Scholar 

  44. IAEA, Objectives for the development of advanced nuclear plants, IAEA-TECDOC-682, Jan. 1993

    Google Scholar 

  45. Jansing W., Teubner H., The high-temperature reactor helium test facility KVK: experiences from 20000 hours of operation, Chemic Ingenieur Technik, 50, No. 11, 1990

    Google Scholar 

  46. Breitling H., Jansing W., Candeli R., Teubner H., KVK and status of the high-temperature component development, IAEA-TECDOC-436, Conference of Gas-Cooled Reactors and Their Applications Jülich, Oct. 1986

    Google Scholar 

  47. Yampolsky J. S., Circulators for helium-cooled reactors, Nuclear Engineering International, Dec. 1971

    Google Scholar 

  48. Cramer H et al., Components of the THTR 300 heat transfer system, Proceedings on Component Design in High-Temperature Reactor using Helium as Coolant, Institute of Mechanical Engineers, June 1972

    Google Scholar 

  49. Xu Yuanhui, Qin Zhenya, Wu Zongxin, Design of the 10MW high-temperature reactor, ICEA, TCM, Petten, 1994

    Google Scholar 

  50. Olson H. G., Brey H. L. and Swart F. E., Fort St. Vrain high-temperature gas-cooled reactor, Nuclear Engineering and Design, 72, 1982

    Article  Google Scholar 

  51. NN, Special issue on helium circulator, Project information on the 300MWel THTR Nuclear Power Plant in Hamm Uentrop, HRB, Mannheim, 1975 till 1987

    Google Scholar 

  52. Habermann H. and Brunet M., The active magnetic bearing enables optimum dumping of flexible rotor, ASME paper No. 84-GT-117, 1984

    Google Scholar 

  53. Fraser W. M., A review of submerged gas circulators as applied to advanced gas-cooled reactors, Nuclear Energy, Oct. 1985

    Google Scholar 

  54. Kosmowski I., Schramm G. and Sörgel G., Turbomachines, VEB Verlag Technik, Berlin, 1987

    Google Scholar 

  55. Zierman E., Ivens G., Experiences with AVR helium circulator, in: Final report on the power operation of the AVR nuclear power plant, JŰL-3448, Oct. 1997

    Google Scholar 

  56. Zhou H. Z. and Wang J., Helium circulator design and testing (HTR-10), Nuclear Engineering and Design, 218, 2002

    Article  Google Scholar 

  57. Gronek M., Rottenbach T. and Worlitz F., A contribution on the investigation of the dynamic behavior of rotating shafts with a hybrid magnetic bearing concept (HMBC) for blow application, Proceeding of the 4th Topical Meeting on High-Temperature Reactor Technology, HTR-2008, Washington, 2008

    Google Scholar 

  58. Rossouw M. A., Development of a blower for the PBMR environment – reliable, versatile and maintenance-free, Proceedings of the 3rd International Topical Meeting on High-Temperature Reactor Technology (HTR-2006), Johannesburg, South Africa, Oct. 2006

    Google Scholar 

  59. Yujie Dong, Fubing Chen, Zuoyi Zhang, Shouying Hu, Lei Shi et al., Simulation and analysis of helium circulator trip at ATWS test at full power on the HTR-10, Proceeding of the 4th Topical Meeting on High-Temperature Reactor Technology, HTR-2008, Washington 2008

    Google Scholar 

  60. Tauveron N., Simulation of performance of centrifugal circulators with vaneless diffuser for GCR applications, Proceeding of the 4th Topical Meeting on High-Temperature Reactor Technology, HTR-2008, Washington, 2008

    Google Scholar 

  61. Molecular sieve, Grace Information MS, 1971

    Google Scholar 

  62. Schulenburg M., Design of the gas purification plant of the process heat reactor PR 500, KFA Report, 1972

    Google Scholar 

  63. Engelhard J., Krüger K., Gottaut H., Investigation of the impurities and fusion products in the AVR coolant gas at an average hot gas temperature of 950 °C, Nuclear Engineering and Design, 34, 1975

    Article  Google Scholar 

  64. The gas circuit of THTR-300, Projektinformation 12 des THTH 300MW-Kraftwerks, Sept. 1978

    Google Scholar 

  65. Reif M., Helium impurities in PNP primary circuit, Paper of the PNP Project, 1980

    Google Scholar 

  66. Noack I., Weiskopf H., The HHV plant design and description, JŰL-1403, Mar. 1977

    Google Scholar 

  67. Noack G., Weiskopf H., Gas purification of HHV plant, in: The HHV Helium Experimental Facility (HHV) – Design and Description of the Plant, JŰL-1403, Mar. 1977

    Google Scholar 

  68. Ziermann E. and Ivens G., Experience with the gas purification in AVR, in: Final Report on the AVR nuclear power plant, JŰL-3448, Oct. 1997

    Google Scholar 

  69. You M. S. et al., The helium purification system of HTR-10, Nuclear Engineering and Design, 218, 2002

    Google Scholar 

  70. Auxiliary system, in: Modern Power Station Practice, Nuclear Power Generation, Vol. 7, Pergamon Press, Oxford, New York, Seoul, Tokyo, 1992

    Google Scholar 

  71. Smidt D., Reactor safety, Springer Verlag, Berlin, Heidelberg, New York, 1979

    Google Scholar 

  72. Rysy W., Pressurized water reactor power plants: safety technology of design, Siemens AG, Unternehmensbereich KWU, 1987

    Google Scholar 

  73. Wachholz W., The decay heat removal concept of the THTR 300 MWel – nuclear power plant Uentrop, Reaktortagung, Germany, 1974

    Google Scholar 

  74. Knüfer H., Shutdown process in the AVR high-temperature reactor, Brennstoff-Wärme-Kraft, 26, 1974

    Google Scholar 

  75. Weicht U., Communication HRB, 1987

    Google Scholar 

  76. Bäumer R., Kalinowski I., THTR – commissioning and operating experience, 11. International Conference on the HTGR, Dimitrovgrad, June 1985

    Google Scholar 

  77. INET, Technical description of HTR-PM project, July 2007

    Google Scholar 

  78. Simon M., Circulators for gas-cooled reactors, Kerntechnik, 11. Jahrg., 1969

    Google Scholar 

  79. Davis P. E., Krase J. M., Nuclear components of Fort St. Vrain, Nuclear Engineering International, Dec. 1969

    Google Scholar 

  80. Houert E. and Knüfer H., Aspects of planning, fabrication and operation of circulators for steam generators, VGB-Fachtagung Dampfkessel und Dampfkesselbetrieb, Germany, 1970

    Google Scholar 

  81. Weisbrodt I., Steinwarz W. and Klein W., Status of the HTR-Module Plant Design, International Atomic Energy Agency, Jülich, 1986

    Google Scholar 

  82. Singh J., Analysis of the thermodynamic transients in the core of a high-temperature reactor, JŰL-937-RG, 1973

    Google Scholar 

  83. Rehm W., Temperature transients in a pebble-bed high-temperature reactor in case of extremely disturbed decay heat removal, Brennstoff-Wärme-Kraft, 33, Nr. 7/8, 1981

    Google Scholar 

  84. Wachholz W., Safety concept of future nuclear power plants HTR 500 and HTR 100, Atomkernenergie-Kerntechnik, Vol. 47, No. 3, 1985

    Google Scholar 

  85. Verfondern K. and Petersen K., Analysis of the temperature and flow fields for the core region of THTR-300 in the 5 hour case, KFA Report, 1977

    Google Scholar 

  86. IAEA, Decay heat removal and heat transfer under normal and accident conditions in gas-cooled reactors, IAEA-TECDOC-757, Aug. 1994

    Google Scholar 

  87. IAEA, Heat transport and after heat removal for gas-cooled reactors under accident conditions: result of simulation of the HTTR-RCCS mockup with the THANPA CSTZ code, IAEA-TECDOC-1163, Jan. 2001

    Google Scholar 

  88. NN, Special issue, Interatom, KVK high-temperature helium test facility, Bensberg, 1983

    Google Scholar 

  89. Jansing W. and Teubner H., The high-temperature helium test facility KVK – experiences from 20000 hours of experimental test operation, Jahrestagung Kerntechnik, 1990

    Google Scholar 

  90. Jansing W., Breitling H., Candeli R. and Teubner H., KVK and status of the high-temperature components development, Technical Committee Meeting on Gas-Cooled Reactors and Their Applications, Jülich, 1986

    Google Scholar 

  91. Bäumer R., THTR 300 – experiences with a progressive technology, Atomwirtschaft, May 1989

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to Kurt Kugeler .

Rights and permissions

Reprints and permissions

Copyright information

© 2019 Tsinghua University Press, Beijing and Springer-Verlag GmbH Germany

About this chapter

Check for updates. Verify currency and authenticity via CrossMark

Cite this chapter

Kugeler, K., Zhang, Z. (2019). Components of the Helium Cycle. In: Modular High-temperature Gas-cooled Reactor Power Plant. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-662-57712-7_6

Download citation

  • DOI: https://doi.org/10.1007/978-3-662-57712-7_6

  • Published:

  • Publisher Name: Springer, Berlin, Heidelberg

  • Print ISBN: 978-3-662-57710-3

  • Online ISBN: 978-3-662-57712-7

  • eBook Packages: EnergyEnergy (R0)

Publish with us

Policies and ethics