Skip to main content
SpringerLink
Log in

Fuel Elements

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

  • 1098 Accesses

Abstract

Fuel elements for high-temperature reactors using coated particle fuel have been developed as block type or spherical variants. The spherical fuel element with TRISO-coated particles is fully developed and qualified in many tests in reactors. The fission product release and the corrosion by impurities are very low in normal operation. By many experiments, it was proven that in case of loss of coolant accidents, a limitation of the maximal temperature to value of 1600 °C is possible and the release of radioactive substances from these fuel elements would stay very small. The maximal fuel temperature in normal operation of a steam cycle power plant will be below 1000 °C, and just some percent of the coated particles will reach these temperatures. The mechanical stresses inside the fuel elements are far away from tolerable limits. The irradiation behavior of the fuel elements has been tested in successful operation of the reactors and in many accompanying tests to qualify the spherical fuel elements. Changes of dimensions during the whole operation time were less than 1 mm as example; the changes of other parameters like heat conductivity, strength, corrosion rate, and further value were limited too. The spherical fuel elements have been tested extensively in the AVR during 20 years of operation. Fourteen different types of fuel elements have been inserted (as example HEU, LEU, BISO coatings, TRISO coatings). The fuel elements reached high burnup values (larger than 100,000 MWd/t), high fast neutron fluence (till 8 × 1021 n/cm2) at very high temperature of operation (THe = 950 °C). Especially, the investigation of the fission product release and the contamination of the helium circuit of the AVR in normal operation were a major topic of development. The release of noble gases as example was so small that a stationary contamination of around 1 Ci/MWth in the helium circuit was realized. This is caused by the excellent retention inside the coated particles. Measurements of the contamination by solid fission products showed a remarkable dependence on the temperature of operation. The data available from the operation of the different HTR plants and from many irradiation experiments deliver today a picture, which allows a prediction of contamination of components and an estimation on possible release rates of radioactive substance during accidents. The formation and transport of graphite dust are known to analyze relevant accident and to design countermeasures. Overall, it can be stated that HTR fuel is fully developed and promises many advantage compared to fuel of other reactors, especially with regard to safety aspects. Further development and improvement of HTR fuel elements are possible: as example coated particles with even better retention capability, reduction of the content of free Uranium in the graphite matrix, protection of the surface against corrosion attack.

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

Access this chapter

Log in via an institution
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. Hrovat M.G., Spener G., Pressed graphitic spherical fuel elements for high-temperature reactors, Ber. Deutsche Keramische Gesselschaft, 43, 1966.

    Google Scholar 

  2. Hackstein K.G., Production of fuel elements for the THTR and the AVR reactor, Atomwirtschaft, 16, 1971.

    Google Scholar 

  3. Nukem, Development of fuel elements for the 300 MWel THTR nuclear power plant, Yearly Report, 1972, 1973.

    Google Scholar 

  4. Wolf L., Ballensiefen G., Fröhling W., Fuel elements of the high-temperature pebble-bed reactor, Nuclear Engineering and Design, Vol. 34, No. 1, 1975.

    Article  Google Scholar 

  5. Gulden T.D., Nickel H., Coated particle fuel, Nuclear Technology 35, 1977.

    Google Scholar 

  6. Nickel H., Balthesen E., Status and possibilities of development of fuel elements for advanced high-temperature reactors in the Federal Republic of Germany, JÜL-1159, Jan. 1975.

    Google Scholar 

  7. Nickel H., Long-term testing of HTR fuel elements in the Federal Republic of Germany, JÜL-Spez, 383, Dec. 1986.

    Google Scholar 

  8. Nickel H., HTR coated particles and fuel elements, HTR/ECS 2002, High-Temperature Reactor School, Cadarache, Nov. 2002.

    Google Scholar 

  9. Hackstein K.G., Heit W., Theymann W., Kaiser G., Status of fuel element technology for high-temperature pebble-bed reactors, Atomenergie-Kerntechnik, Vol. 47, No.3, 1985.

    Google Scholar 

  10. Ivens G., Wimmers M., The AVR as test bed for fuel elements, in: AVR Experimental High-Temperature Reactor, VDI-Verlag, Düsseldorf, 1990.

    Google Scholar 

  11. Heit W., Huschka H., Rind W., Kaiser G., Status of qualification of high-temperature reactor – fuel elements spheres, Nucl. Technology 69, 1985.

    Article  Google Scholar 

  12. Nabielek H., Kaiser G., Huschka H., Rogoβ M., Wimmers M., Theymann W., Fuel for pebble-bed HTRs, Nucl. Engin. Design 78, 1984.

    Article  Google Scholar 

  13. Teuchert E., Bohl L., Rütten H.J., Haas K.A., The pebble-bed high-temperature reactor as a source of nuclear process heat, Vol.2, Core Physics Studies: JÜL-1114-RG, Oct. 1974.

    Google Scholar 

  14. Verfondern K., Numerical analysis of the 3-dimensional stationary temperature and flow distributions in the core of a pebble-bed high-temperature reactor, JÜL-1826, 1983.

    Google Scholar 

  15. Williams D.F., Fuels for VHTR, The 2004 F. Joliot + O. Hahn Summer School, Cadarache, Aug/Sept, 2004.

    Google Scholar 

  16. Chunhe Tang, Shijiang Xu, Zhichang Xu, Junguo Zhu, Xueliang Qiu, Ende Li, Spherical fuel elements for 10 MW HTGR, Journal of Tsinghua University, Vol. 34, No. 54, Sept. 1994.

    Google Scholar 

  17. Layout of the core of gas-cooled high-temperature reactors; quasi stationary status in the pebble bed, KTA-Regal 3102, 4; Fassung Nov. 1984.

    Google Scholar 

  18. Balthesen E., Ragoβ H., Irradiation behavior of fuel elements for pebble-bed reactors, Intern. Conf. on Physical Metallurgy of Reactor Fuel Elements, Sept. 1973.

    Google Scholar 

  19. Delle W., Koizlik K., Nickel H., Graphitic materials for the application in nuclear reactors, Vol. 1 and 2; Verlag Karl Thiemig, München, 1979/1983.

    Google Scholar 

  20. Nickel H., Nabielek H., Pott G., Mehner A. W., Long-time experience with the development of HTR fuel elements in Germany, Nuclear Engineering and Design, 217, 2002.

    Article  Google Scholar 

  21. Teuchert E., Fuel cycles of the pebble-bed high-temperature reactors in the computer simulation, JÜL-2069, June 1986.

    Google Scholar 

  22. Teuchert E., Rütten H.J., Werner H., Haas K.A., Closed cycles in the pebble-bed HTR, JÜL-1569, Jan. 1979.

    Google Scholar 

  23. Toscano E., Post irradiation examination of HTR fuel elements HTR/ECS 2002, High Temperature Reactor School, Cadarache, Nov. 2002.

    Google Scholar 

  24. Schenk W., Gontard R., Nabilek H., Performance of HTR fuel samples under high irradiation and accident simulation conditions, with emphasis on test capsules HFR-P4 and SL-P1, JÜL-3373, April 1997.

    Google Scholar 

  25. IAEA, Fuel performance and fission product behavior in gas-cooled reactors, IAEA-TECDOC 978, Nov. 1997.

    Google Scholar 

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

    Google Scholar 

  27. Wolf L., Ballensiefen G., Fröhling W., Fuel elements of the high-temperature pebble-bed reactor, Nuclear Engineering and Design, Vol. 33, No. 1, 1975.

    Article  Google Scholar 

  28. Teuchert E., Maly V., Haas K.A., Basic study for the pebble-bed reactor with OTTO fuel cycle, JÜL-858-RG, May 1972.

    Google Scholar 

  29. Maly V., Schulten R., Teuchert E., 500 MWth – pebble-bed reactors for process heat in one path loading, Atomwirtschaft, 17, April 1972.

    Google Scholar 

  30. Eugelhard J., Final report on the construction and the start of operation of the AVR atomic experimental power plant, BMBW-FBK 72–23, Dec. 1972.

    Google Scholar 

  31. Wimmers M., The behavior of spherical HTR fuel elements during mass tests in the AVR reactor, Dissertation, RWTH Aachen, Jan. 1977.

    Google Scholar 

  32. Ivens G., Wimmers M., The AVR as test bed for fuel elements in AVR experimental high-temperature reactor, VDI-Verlag, Düsseldorf, 1990.

    Google Scholar 

  33. Burck W., Nabielek H., Pott G., Ragoβ W.E., Ring W., Röllig K., Performance of spherical fuel elements for advanced HTRs, Trans. EN Conf. Europ. Nucl. Soc. 1979.

    Google Scholar 

  34. Schulze R.E., Schulze H.A., Rind W., Graphitic matrix materials of spherical HTR fuel elements, JÜL-Spez-167, July 1982.

    Google Scholar 

  35. Nickel H., HTR coated particles and fuel elements, historical basis, HTR/ECS 2002, High-Temperature Reactor School, Cadarache, Nov. 2002.

    Google Scholar 

  36. Ziermann E., Ivens G., Final report on the power operation of the AVR experimental nuclear power plant, JÜL-3448, Oct. 1997.

    Google Scholar 

  37. Von der Decken C.B., Pebble-bed mechanics, in AVR experimental high-temperature reactors, VDI-Verlag, Düsseldorf, 1990.

    Google Scholar 

  38. Weisbrodt I.A., Summary report on the technical experiences from high-temperature helium turbo machinery testing in Germany, IAEA, TECDOC 899, 1996.

    Google Scholar 

  39. Nickel H., Irradiation behavior of advanced fuel elements for the helium-cooled high-temperature reactor (HTR), JÜL-Spez-565, May 1990.

    Google Scholar 

  40. Pott G., Kirch N., Kracynski S., Nickel H., Theenhaus R., Qualification of HTR fuel and graphite in European Material Testing Reactors, Multipurpose Research Reactors, Proc. Conf. Grenoble, 1987, IAEA-SM-300/20, Vienna 1988.

    Google Scholar 

  41. Mehner A.W., Heit W., Röllig K., Ragoβ H., Müller H., Spherical fuel elements for HTR manufacture and qualification by irradiation testing, Journal of Nuclear Materials 171, 1990.

    Article  Google Scholar 

  42. Nabielek H., Kaiser G., Huschka H., Ragoβ H., Wimmers M., Theymann W., Fuel for pebble-bed HTRs, Nuclear Engineering and Design 78, 1984.

    Article  Google Scholar 

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

    Article  Google Scholar 

  44. Ziermann E., Operation experience of AVR, VDI-Berichte, Nr. 729, 1989.

    Google Scholar 

  45. Kröger W., Benefit of safety assessments in AVR experimental high-temperature reactor, VDI-Verlag, Düsseldorf, 1990.

    Google Scholar 

  46. Mehner A.W., Heit W., Rölling K., Ragoβ H., Müller H., Spherical fuel elements for HTR; manufacture and qualification by irradiation testing, Journal of Nuclear Materials, 171, 1990.

    Article  Google Scholar 

  47. Elter C., The strength of the reflector of a pebble-bed reactor, Dissert, RWTH Aachen, 1973.

    Google Scholar 

  48. Nieder R., Hilgedick R., Vey K., The behavior of radioactive noble gases in the primary circuit of a high-temperature reactor, VGB-Konferenz “Forschung in der Kraftwerkstechnik”, Essen, March 1983.

    Google Scholar 

  49. Wawrzik U., Ivens G., Operational monitoring of the release behavior of the AVR core, IAEA specialists meeting on fission product release and transport in gas-cooled reactors, Berkeley Nuclear Laboratories, Gloncester UK, Oct. 1985.

    Google Scholar 

  50. Schenk W., Pitzer D., Nabielek H., Fission product release of pebble-bed fuel elements at accident temperatures, JÜL-2721, Jan. 1993.

    Google Scholar 

  51. Verfondern K., Martin R.C., Moormann R., Methods and data for HTGR fuel performance and radio nuclide release modeling during normal operation and accidents for safety analysis, JÜL-2721, Oct. 1993.

    Google Scholar 

  52. Schenk W., Verfondern K., Nabielek H., Toscano E.H., Limits of LEU TRISO particle performance, Proceeding HTR in International HTR Fuel Seminar, Brussels, Feb. 2001.

    Google Scholar 

  53. IAEA, Full performance and fission product behavior in gas-cooled reactors, IAEA TECDOC 978, 1997.

    Google Scholar 

  54. Tang C.H., Tang Y.P., Zhu Q., et al, Research and development of fuel elements for Chinese 10 MW high-temperature gas-cooled reactor, Journal of Nuclear Science and Technology, 37, 2000.

    Article  Google Scholar 

  55. Tang C. et al, Fuel irradiation of the first batches produced for the Chinese HTR-10, Nuclear Engineering and Design, 236, 2006.

    Article  Google Scholar 

  56. Layout of the reactor core of gas-cooled high-temperature reactors, Part 5: Systematic and Statistic Failure During the Thermohydraulic Design of the Core of Pebble-bed Reactors, KTA-3102.5, June 1986.

    Google Scholar 

  57. Hahn W. and Achenbach E., Estimation of the heat transfer coefficient at the wall of systems with pebble-bed under flow conditions, JÜL-2093, Oct. 1986.

    Google Scholar 

  58. Schenk W., Pott G., Nabielek H., Fuel accident performance testing for small HTRs, Journal of Nuclear Materials, 171, 1998.

    Article  Google Scholar 

  59. Kubascheweki P., Heinrich B., Heit W., Corrosion of graphitic reactor components in operation and in accidents, Deutsche Reactortagung, 1984.

    Google Scholar 

  60. Loeniβen K.J., Analysis of the dependence of pressure of graphitic steam reaction in the process diffusion region in connection with water ingress accidents in the high-temperature reactor, Dissert. RWTH Aachen, 1987.

    Google Scholar 

  61. Wischnewski R., Analysis of the forming of water gas in case of accidents in HTR reactors for the example of a planned rise of hot gas to 950 °C in the AVR reactor, Dissert. RWTH Aachen, 1974.

    Google Scholar 

  62. Wolters J., Breitbach G., Moormann R., Air and water ingress accidents in an HTR-Module of side-by-side concept, Proceed. Spec. Meeting, Oakridge, 1985.

    Google Scholar 

  63. NN, Special information, corresponding to THTR publications since 1968 (Euratom, THTR project).

    Google Scholar 

  64. Fröhling W. et al, Chemical stability of innovative nuclear reactors, JÜL-2960, Aug. 1994.

    Google Scholar 

  65. Nieder R., Sträter W., Long-time behavior of impurities in an HTR primary circuit, VGB conference “Chemie im Kraftwerk”, Essen, Oct. 1987.

    Google Scholar 

  66. Zelkowski J., Burning coal, VGB Technische Vereinigung der Groβkraftwerksbetriebe, 1986.

    Google Scholar 

  67. Hinssen K.H., Katscher W., Moormann R., Kinetics of the graphite/oxygen/reaction in the porous diffusion region, Part I: JÜL-1987, Nov. 1983; Part II: JÜL-2052, Apr. 1986.

    Google Scholar 

  68. Hurtado Gutierrez A.M., Analysis of massive air ingress into high-temperature reactors, Dissert. RWTH Aachen, Dec. 1990.

    Google Scholar 

  69. Schlögl B., Oxidation kinetics of innovative carbon materials in case of extreme accidents of air ingress into the HTR and for application of graphite waste management and processing, Diss. RWTH Aachen, 2010.

    Google Scholar 

  70. Roes J., Experimental analysis of graphite corrosion and forming of aerosols during air ingress into the core of a pebble-bed high-temperature reactor, JÜL-2956, 1994.

    Google Scholar 

Download references

Author information

Authors and Affiliations

  1. Institute for Reactor Safety and Reactor, RWTH Aachen University, Jülich, Germany

    Kurt Kugeler

  2. Institute of Nuclear and New Energy Tech, Tsinghua University, Beijing, China

    Zuoyi Zhang

Authors
  1. Kurt Kugeler
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Zuoyi Zhang
    View author publications

    You can also search for this author in PubMed Google Scholar

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). Fuel Elements. In: Modular High-temperature Gas-cooled Reactor Power Plant. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-662-57712-7_4

Download citation

  • DOI: https://doi.org/10.1007/978-3-662-57712-7_4

  • 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

Search

Navigation