Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan
2007 Fall Meeting
Session ID : D40
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Core Characteristics of Small Lead Alloy Cooled Fast Reactor For Various Fuel Types and Cladding-Structure Materials
Abu Khalid Rivai*Minoru Takahashi
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Abstract
Effects of various fuel types and cladding-structure materials on neutronics of reactor core for a high temperature small lead alloy cooled fast reactor have been investigated analytically. The fuel types were nitride fuel, oxide fuel and metal fuel. The cladding-structure materials were steel and ceramic. Different enrichment in inner core and outer core was done for relatively flat neutron flux distributions and power density distribution. The core design was optimized using natural uranium blanket and fuel for long life-core with reshuffling interval of 10 years. The neutronic characteristics considered are the neutron energy spectrum, the criticality, the neutron flux distribution, the power density distribution, the void coefficient and the fuel burn up.
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© 2007 Atomic Energy Society of Japan
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