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- W1970439811 abstract "The physical behavior of integral data in an infinite medium has been evaluated for incident fusion neutrons with the help of the 3-D Monte Carlo Code. In a fusion reactor blanket with finite dimension, the integral quantities will be more or less different from the infinite medium results, depending on the neutron leakage fraction. Design studies foresee reduction of the neutron leakage out of the blanket to very low levels in order to prevent nuclear heating in superconducting fusion magnets and to keep all neutrons primarily in the coolant. The most important materials in fusion technology, namely tritium, beryllium, lead, and uranium have been investigated in an infinitive medium. The main purpose of this work is to calculate integral neutronic data for incident 14.1-MeV (D,T) fusion source neutrons in an infinite medium for the most important materials in fusion technology, namely lithium, beryllium, lead and uranium. The study concludes the calculation of the integral tritium breeding ratio, 239Pu breeding rate, neutron multiplication ratio through (n, x) and fission reactions and that of the heat release in those mixtures that are composed, first when natural uranium and 238U, are mixed with natural lithium or 6Li for a volume fraction from 0% to 100%, and then, the variable uranium–lithium composition is mixed with Be or Pb for a volume fraction from 0% to 100%." @default.
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- W1970439811 date "2004-06-01" @default.
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- W1970439811 title "Integral data for most important materials, namely lithium, beryllium, lead and uranium in infinite medium per fusion neutron" @default.
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- W1970439811 doi "https://doi.org/10.1016/j.enconman.2003.09.008" @default.
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