Status of Research and Development of the Lead-Alloy-Cooled Fast Reactor

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概要

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• The U.S. Department of Energy is leading an international initiative to develop the Generation IV Nuclear Reactor. The vast majority of the nation’s 104 reactors are type Generation II; Generation III designs (i.e., Advanced Boiling Water Reactor) and have only been built overseas (Korea, Japan). The Generation IV reactor concepts must meet the following criteria: (1) economic competitiveness, (2) inherent safety, (3) minimization of waste, (4) nonproliferation enhancement, and (5) provide social benefit (electricity, “hydricity”). One of the concepts under evaluation is the lead-cooled (Pb) or lead-alloy-cooled (primarily Pb–Bi) fast reactor. Lead/Lead-bismuth reactor cooling offers enhanced safety and reliability in contrast to other liquid metals through its properties, these being chemical inertness with air and water, high atomic number, low vapor pressure at operating temperatures, and high boiling temperature. The only significant drawback is “corrosiveness,” or incompatibility with fuel cladding and structural materials. The review presents the state of development not only of lead/reactor material compatibility research, but also of the extent of international activities toward realization of a Pb/Pb–Bi-cooled fast reactor.

• 一般社団法人 日本原子力学会の論文
• 2003-08-25

著者

• Loewen Eric

  Idaho National Engineering And Environmental Laboratory

• Tokuhiro Akira

  Nuclear Engineering Department University Of Missouri-rolla

関連論文

• The Chemical Kinetics of Alkaline Extraction of Tellurium from Lead-Bismuth Eutectic
• Status of Research and Development of the Lead-Alloy-Cooled Fast Reactor
• Benchmark Simulation of Turbulent Flow through a Staggered Tube Bundle to Support CFD as a Reactor Design Tool. Part I : SRANS CFD Simulation
• Benchmark Simulation of Turbulent Flow through a Staggered Tube Bundle to Support CFD as a Reactor Design Tool. Part II : URANS CFD Simulation

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