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

  • Cinotti L
  • Smith C
  • Artioli C
  • et al.
Springer US, (2010), 2749-2840
DOI: 10.1007/978-0-387-98149-9_23
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Abstract

A Compendium of Reactor Technology

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APA

Cinotti, L., Smith, C. F., Artioli, C., Grasso, G., & Corsini, G. (2010). Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design. In Handbook of Nuclear Engineering (pp. 2749–2840). Springer US. https://doi.org/10.1007/978-0-387-98149-9_23

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