Homogeneous reactors fueled with

A homogeneous reactor fueled with a dilute, highly enriched UO2SO4 solution is potentially capable of operating without removing fission... 

Construction of the reactor (Homogeneous Reactor Experiment No. 1) was started in September 1950, and completed in January 1952. After a period of nonnuclear testing with a natural-uranium fuel solution, HRE-1 reached criticality on April 15, 1952. Early in 1954 it was dismantled after successfully demonstrating the nuclear and chemical stability of a moderately high-power-density circulating-fuel reactor, fueled with a solution of enriched uranyl sulfate. 

J. J. Went and H. de Rruyn, The Design of a Small Scale Prototype of a Homogeneous Power Reactor Fueled with Uranium Oxide Suspension, in Proceedings of the International Conference on the Peaceful Uses of Atomic Energy, Vol. 3. New York United Nations, 1956. (P/936)... 

In processing homogeneous reactor fuel, a transition from a heavy- to a natural-water system is desirable if final processing is to be performed in conventional solvent extraction equipment. Such a transition must be accomplished with a minimum loss of D2O and a minimum contamination of... 

Initial-State Nuclear Characteristics of Two-Region, Homogeneous, Molten Fluoride-Salt Reactors Fueled with... 

Fig. 14-4. Initial fuel regeneration in two-region, homogeneous, molten fluoride-salt reactors fueled with U . Total power, 600 Mw (heat) external fuel volume, 339 ft core and blanket salts No. 1.

Initial-State Nuclear Characteristics of Two-Region, Homogeneous, Molten Fluoride-Salt Reactors Fueled with Fuel salt No. 2 37 mole % BeF2 + 63 mole % LiF -h UF4 + TI1F4. 

A radiochemical method for the determination of uranlum-237 Is based on complexlng the uranyl Ion In alkaline solution with hydroxylamlne hydrochloride, followed by scavenging with zirconium hydroxide and extraction of the uranium from hydrochloric acid solution with trllsooctylamlne-xylene. The technique has been applied successfully to the determination of uranlum-237 homogeneous reactor fuel solutions. 

The process route of uranium as nuclear fuel is shown in Fig. 11.7. It begins with processing of uranium ores, from which pure uranium compounds are produced. These may be used in the natural isotopic composition or transformed into other compounds suitable for isotope separation. The next step is the production of fuel elements for the special requirements of reactor operation. Solutions of uranium compounds are applied only in homogeneous reactors. 

The design of fuel elements depends on the type of reactor and on the operating conditions. Fabrication of fuel elements does not apply for homogeneous reactors in which the fuel is used in the form of a solution of uranyl sulfate or uranyl [ N] nitrate. In heterogeneous reactors, the fuel is applied in the form of metals or alloys or in the form of ceramic substances, such as UO2, UC or mixtures with other components. 

Let the rate of energy per unit volume generated in a solid cylinder or a solid sphere be u" (r) = u , the radius and the thermal conductivity of the cylinder or the sphere be R and k(T) = kr (alternate notations ur and kr are used for convenience in the following formulation). Under steady conditions, the total energy generated in the cylinder or sphere is transferred, with a heat transfer coefficient h, to an ambient at temperature Too. This cylinder could be one of the fuel rods of a reactor core, or one of the elements of an electric heater, and the cylinder or sphere could be a bare, homogeneous reactor core. We wish to determine the radial temperature distribution. 

The present study represents an attempt to study the problem of control rod calibration during a xenon transient from a purely analytic point of view and then correlate theory with experiment to obtain the desired results in the best possible approximations. Particulars of the problem are described as follows. Suppose that a thermal reactor, fueled homogeneously with uranium-235, is maintained at criticality during the rising phase of a xenon transient by the continuous motion of a control rod. Then a control rod (or set of control rods) is suddenly pulled at = o- The approximate subsequent behavior of the flux has already been described. It is desired to find the reactivity thus introduced by pulling the rod x inches. 

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