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[en] The influence of the presence of ²⁴⁰Pu in commercial plutonium on neutron lifetime has been investigated in order to analyse its effects in nuclear explosives. The necessary neutron spectrum has been obtained through 100 groups calculations in S₈-P₃ approximation. Investigation of the energy dependent and averaged neutron lifetime shows that the presence of ²⁴⁰Pu increases the neutron lifetime to a moderate degree which can decrease the energy release of the nuclear bomb only in a limited scale. (author)

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[en] Thermionic reactors with ²³³U as fuel and beryllium as moderator are appropriate as primary or secondary energy sources in space craft. A neutron physics analysis of such a reactor is presented. All neutron physics calculations have been carried out with the help of multigroup Ssub(N) methods. 123 energy groups, S₄ - P₃ approximation by one dimensional and 4 energy groups, S₄ - P₁ approximation by two dimensional calculations have been used. Some integral values and neutron production densities are given as characteristic properties of the reactor. (author)

[en] In recent work, the regeneration of CANDU spent fuel in a deuterium-tritium (D-T)-driven hybrid reactor blanket has been investigated. Scientists and engineers now have begun to believe that the economic feasibility of advanced fusion fuel cycles will be possible soon after the first generation of reactors based on conventional fusion fuel (D-T). In the work reported in this paper, a semicatalyzed deuterium-deuterium (D-D) fusion reactor has been investigated to drive a fissile blanket that contains CANDU spent fuel. The fuel regeneration has been studied coupled with substantial electricity production in situ. The main conclusions can be summarized as follows: (1) The spent-fuel regeneration in a semicatalyzed (D-D) fusion-fission blanket proceeds faster than the pure (D-T)-driven hybrid blanket per incident fusion neutron energy load at the first wall; (2) The high blanket multiplication factor M allows one to produce abundant electricity in situ; (3) The blanket produces a substantial amount of tritium for satellite (D-T) fusion reactors; (4) The spent fuel can be regenerated to be used in an advanced CANDU reactor with thorium recycling, even to the degree necessary for use in a conventional LWR. 1 ref., 1 fig

[en] Efforts are made at the College of Engineering, King Saud University, Riyadh to lay out the main structure of a prototype experimental fusion and fusion-fission (hybrid) reactor blanket in cylindrical geometry. The geometry is consistent with most of the current fusion and hybrid reactor design concepts in respect of the neutronic considerations. Characteristics of the fusion chamber, fusion neutrons and the blanket are provided. The studies have further shown that 1 GWe fission-fusion reactor can produce up to 957 kg/year which is enough to fuel five light water reactors of comparable power. Fuel production can be increased further. 29 refs

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[en] The fusion reactor chamber is simulated by a cylindrical cavity where the fusion neutrons are generated along the cylinder axis by a movable target. This becomes possible due to the linear chamber of the Boltzmann Transport Equation. The first wall is simulated by a 1.3 cm thick stainless steel, as in TFTR experiments. The fuel zone is made up by an hexagonal arrangement of the fuel rods to simulate a gas-cooled blanket. The tritium breeding zone is made of Li/sub 2/O, imbedded in the form of a sandwich structure into the graphite reflector. This arrangement reduces the radial leakage significantly, in favor of Li/sup 6/(n,α)T breeding reaction. In this design, lithium produces tritium more efficiently, compared to a blanket where it would be placed only in one blanket zone. The calculations have shown that, as a result of the sandwich structure, the radial leakage is depressed by a factor more than 2, using a (D,T) driver and natural Li/sub 2/O. This factor increases to 13, using a (D,D) driver and 90% enriched Li/sup 6/. Multidimensional neutronic analysis has shown that due to the simplicity of the blanket geometry and due to the clean symmetry around the axis of the cylinder, one-dimensional calculations would be sufficient to interpret the experiments over a wide range of the blanket

No abstract available