Skip to main content

Converter Reactors with a Thermal Neutron Spectrum

  • Chapter
Nuclear Fission Reactors

Part of the book series: Topics in Energy ((TENE))

  • 225 Accesses

Abstract

At present, nuclear power generation is mainly based on light water reactors (LWR’s) designed as pressurized water reactors (PWR’s) or boiling water reactors (BWR’s) (see Table 1–1). LWR’s use enriched uranium fuel, which makes for greater flexibility in the choice of reactor core materials, especially allowing normal (light) water to be used as a coolant and moderator. PWR’s deliver the heat generated in their reactor core to water circulating under high pressure in primary coolant circuits. From here the heat is transferred to a secondary coolant system via a steam generator to produce steam driving a turbo-generator system. In BWR’s with direct cycle, the steam for the turbo-generator system is generated right in the reactor core and sent directly to the turbo-generator. PWR’s and BWR’s have been advanced to a high level of technical maturity in more than twenty years of development. They are built in unit sizes up to 1300 MW (e). The most important design data of large PWR and BWR power plants are listed in Table 4–1.

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 39.99
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 54.99
Price excludes VAT (USA)
  • Compact, lightweight 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

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

Selected Literature

Light water reactors

  • Druckwasserreaktor. Erlangen: Kraftwerk Union AG, K/10567 (1981).

    Google Scholar 

  • General Description of a Boiling Water Reactor. San Jose, Cal.: General Electric Company. 1978.

    Google Scholar 

  • Lamarsh, J.R.: Introduction to Nuclear Engineering. Reading, Mass.: Addison-Wesley. 1975.

    Google Scholar 

  • Lewis, E.E.: Nuclear Power Reactor Safety. New York: John Wiley. 1977.

    Google Scholar 

  • Märkl, H.: Core Engineering and Performance of KWU Pressurized Water Reactors. Erlangen: Kraftwerk Union AG. 1976.

    Google Scholar 

  • Nero, A.v.: A Guidebook to Nuclear Reactors. Berkeley-Los Angeles-London: University of California Press. 1979.

    Google Scholar 

  • Druckwasserreaktoren für Kernkraftwerke (Oldekop, W., ed.). München: Karl Thiemig. 1974.

    Google Scholar 

  • Sauer, A.: Siedewasserreaktoren für Kernkraftwerke. Berlin: AEG Telefunken, Handbücher Band 10. 1969.

    Google Scholar 

  • Smidt, D.: Reaktor-Sicherheitstechnik. Berlin-Heidelberg-New York: Springer. 1979.

    Google Scholar 

  • Technical Evaluation of Bids for Nuclear Power Plants - A Guide Book. Vienna: International Atomic Energy Agency, TR 204 (1981).

    Google Scholar 

Gas cooled reactors

  • Boyer, V.S., et al: High Temperature Reactors. In: Nuclear Energy Maturity, Proc. European Nuclear Conference, Paris, 21–25 April, 1975 (Zaleski, P., ed.). Vol. 2, pp. 191–217. Oxford: Pergamon Press. 1976.

    Google Scholar 

  • Dahlberg et al: HTGR Fuel and Fuel Cycle Summary Description. San Diego, Cal.: General Atomic Company, GA-A 12801 (1974).

    Google Scholar 

  • Development Status and Operational Features of the High Temperature Gas Cooled Reactor. Palo Alto, Cal.: Electric Power Research Institute, EPRI NP-142 (1976).

    Google Scholar 

  • Engelmann, P., Oehme, H.: Ziele der HTR-Entwicklung für Stromerzeugung und Prozeßwärme. Atomwirtschaft/Atomtechnik 22, 484–490 (1977).

    Google Scholar 

  • Fassbender, J. et al.: Zur Störfalltopologie des Hochtemperaturreaktors. Atomkernenergie/Kerntechnik 37, 81–86 (1981).

    Google Scholar 

  • Harder, H., et al: Das 300 MWe Thorium-Hochtemperatur-Kernkraftwerk (THTR). Atomwirtschaft/Atomtechnik 16, 238–245 (1971).

    Google Scholar 

  • Schulten, R., et al: The Pebble-bed High Temperature Reactor as a Source of Nuclear Process Heat. Kernforschungsanlage Jülich, Jül 1115-RG (1974).

    Google Scholar 

  • Wessmann, G.L., Mofette, T.R.: Safety Design Bases for HTGR. Nuclear Safety 14, 618–634 (1973).

    Google Scholar 

Heavy water reactors

  • Foster, J.S., Critoph, E.: The Status of the Canadian Nuclear Programme and Possible Future Strategies. Annals of Nuclear Energy, Vol. 2, pp. 689–703. Oxford: Pergamon Press. 1975.

    Google Scholar 

  • McIntyre, H.C.: Natural Uranium Heavy Water Reactors. Scientific American 233 (4), 17–27 (1975).

    Article  Google Scholar 

  • Smith, H.A.: A Review of the Development Status of CANDU Nuclear Power Plants. In: Nuclear Energy Maturity, Proc. European Nuclear Conference, Paris, 21–25 April, 1975 (Zaleski, P., ed.). Vol. 2, pp. 38–44. Oxford: Pergamon Press. 1976.

    Google Scholar 

  • Study of the Development Status and Operational Features of Heavy Water Reactors, Palo Alto, Cal: Electric Power Research Institute, EPRI NP-365 (1977).

    Google Scholar 

  • Woodhead, L.W., Ingolfsrud, L.J.: Performance of Canadian Commercial Nuclear Units and Heavy Water Plants. In: Nuclear Energy Maturity, Proc. European Nuclear Conference, Paris, 21–25 April, 1975 (Zaleski, P., ed.), Vol. 2, pp. 103–112. Oxford: Pergamon Press. 1976.

    Google Scholar 

Near breeders and thermal breeder reactors

  • Conceptual Design Study of a Single Fluid Molten Salt Breeder Reactor. Oak Ridge National Laboratory, ORNL-4541 (1971).

    Google Scholar 

  • The Development Status of Molten Salt Breeder Reactors. Oak Ridge National Laboratory, ORNL-4812 (1972).

    Google Scholar 

  • Perry, A.M., Weinberg, A.M.: Thermal Breeder Reactors. In: Annual Review of Nuclear Science, Vol. 22, pp. 317–354. Palo Alto, Cal: Annual Reviews Inc. 1972.

    Google Scholar 

  • Status and Prospects of Thermal Breeders and Their Effect on Fuel Utilization. Vienna: International Atomic Energy Agency, IAEA Technical Report Series No. 195 (1979).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Rights and permissions

Reprints and permissions

Copyright information

© 1983 Springer-Verlag Wien

About this chapter

Cite this chapter

Kessler, G. (1983). Converter Reactors with a Thermal Neutron Spectrum. In: Nuclear Fission Reactors. Topics in Energy. Springer, Vienna. https://doi.org/10.1007/978-3-7091-7622-1_4

Download citation

  • DOI: https://doi.org/10.1007/978-3-7091-7622-1_4

  • Publisher Name: Springer, Vienna

  • Print ISBN: 978-3-7091-7624-5

  • Online ISBN: 978-3-7091-7622-1

  • eBook Packages: Springer Book Archive

Publish with us

Policies and ethics