Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design

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Fifth chapter from "A Compendium of Reactor Technology" discussing the history and design of lead-cooled fast reactors in nine sections: Lead-cooled Fast Reactor (LFR) Development, Design Criteria and General Specifications, Neutronics, Lead Properties, Compatibility of Structural Materials with Lead, Core, Reactor System, Decay Heat Removal System, and Nuclear Island.

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100 p. (9.9 MB)

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Smith, Craig; Cinotti, L.; Artoli, C. & Grasso, G. February 22, 2010.

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This chapter is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 1042 times, with 11 in the last month. More information about this chapter can be viewed below.

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  • Main Title: Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design
  • Added Title: A Compendium of Reactor Technology

Description

Fifth chapter from "A Compendium of Reactor Technology" discussing the history and design of lead-cooled fast reactors in nine sections: Lead-cooled Fast Reactor (LFR) Development, Design Criteria and General Specifications, Neutronics, Lead Properties, Compatibility of Structural Materials with Lead, Core, Reactor System, Decay Heat Removal System, and Nuclear Island.

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100 p. (9.9 MB)

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  • A Compendium of Reactor Technology, "Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design," 2010, Springer: Karlsruhe, Germany, pp. 2752-2769

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  • Report No.: LLNL-BOOK-424323
  • Grant Number: W-7405-ENG-48
  • Office of Scientific & Technical Information Report Number: 1020358
  • Archival Resource Key: ark:/67531/metadc840495

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  • February 22, 2010

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  • May 19, 2016, 3:16 p.m.

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Smith, Craig; Cinotti, L.; Artoli, C. & Grasso, G. Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design, chapter, February 22, 2010; Livermore, California. (https://digital.library.unt.edu/ark:/67531/metadc840495/: accessed September 12, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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