Abstract: In a cooling structure and a cooling method for a control rod drive mechanism and in a nuclear reactor, a housing (59) in which magnetic jacks are housed is fixed to an upper portion of a reactor vessel (41), and an air intake unit (102) that takes cooling air into the housing (59), a first exhaust duct (104) that is arranged side by side with the air intake unit (102) in a circumferential direction of the housing (59), into which cooling air in the housing (59) is suctioned through a first inlet (109) at a lower portion thereof, and that guides the cooling air upward, a second exhaust duct (105) that is disposed below the air intake unit (102), into which cooling air in the housing (59) is suctioned through a second inlet (110), and that guides the cooling air to the first exhaust duct (104), and a discharging unit (111) that is formed at an upper portion of the housing (59) and discharges cooling air in the first exhaust duct (104) to the exterior are provided.

Abstract: The present invention relates generally to the field of compensation methods for nuclear reactors and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear reactors. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear reactor. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear reactor through a method that does not rely on moving components into or out of a reactor core, nor does the method of the present invention rely on the constant repositioning of control rods within a nuclear reactor in order to maintain a critical state.

Abstract: In a nuclear power plant making use of a high temperature gas cooled reactor, it is necessary, prior to commencing power generation and connection of a generator to an electrical distribution grid, to condition the power generation circuit of the plant. This involves creating stable conditions within the power generation circuit. To this end, the plant includes a start-up blower system for circulating working fluid, typically helium, around the power generation circuit until the desired conditions are satisfied. The start-up blower system typically includes a normally open in-line valve, at least one blower connected in parallel with the in-line valve and a normally closed isolation valve connected in series with the blower. Conditioning the power generation circuit will typically include stabilizing the pressure in the circuit at between 10 bar and 50 bar.

Abstract: A fast reactor core in which a coolant flows comprises a plurality of fuel assemblies each loaded with a fissionable material and a plurality of gas sealed assemblies disposed between the fuel assemblies and sealed with a gas, wherein a surface level of the coolant in the gas sealed assembly changes from an axially upper portion including a core top level to an axially lower portion at a time of core power increase or a core coolant flow quantity decrease. Each of the gas sealed assemblies includes an inner cylindrical member for reducing a horizontal cross sectional area of the flow of the coolant at a portion in height corresponding to an axial central portion of the core and the cylindrical member includes a member for generating heat by radiation.

Abstract: A pneumatic safety system for a nuclear reactor includes a containment vessel containing He.sub.3 at high pressure communicating with a nuclear core by way of a conduit system which includes hollow pipes situated adjacent rods of fissionable material inside the core area. A rupturable diaphragm is interposed in the conduit system and is connected by a plurality of heat-pipes to the core area. The heatpipes respond to changes in core temperature and at a critical temperature cause the diaphragm to rupture thus allowing neutron absorbing gas under high pressure to quickly flood the core shutting down the nuclear reaction.

Abstract: A control element for reactivity control of a fission source provides an atomic density of .sup.3 He in a control volume which is effective to control criticality as the .sup.3 He is spin-polarized. Spin-polarization of the .sup.3 He affects the cross section of the control volume for fission neutrons and hence, the reactivity. An irradiation source is directed within the .sup.3 He for spin-polarizing the .sup.3 He. An alkali-metal vapor may be included with the .sup.3 He where a laser spin-polarizes the alkali-metal atoms which in turn, spin-couple with .sup.3 He to spin-polarize the .sup.3 He atoms.

Abstract: A reactor control system for controlling the reactivity of the core of a fission-type nuclear reactor is provided. The control system includes a reservoir containing a control gas having a high neutron cross section. At least one conduit which communicates with the reservoir to provide a fluid passage which extends at least partially into the core of the reactor. A system is provided for controlling the pressure of the control gas in the conduit.

Abstract: A control element for reactivity control of a fission source provides an atomic density of .sup.3 He in a control volume which is effective to control criticality as the .sup.3 He is spin-polarized. Spin-polarization of the .sup.3 He affects the cross section of the control volume for fission neturons and hence, the reactivity. An irradiation source is directed within the .sup.3 He for spin-polarizing the .sup.3 He. An alkali-metal vapor may be included with the .sup.3 He where a laser spin-polarizes the alkali-metal atoms which in turn, spin-couple with .sup.3 He to spin-polarize the .sup.3 He atoms.

Abstract: A moderator control apparatus is provided for use with a fuel assembly to improve fuel utilization in thereby reducing fuel cycle costs. The apparatus includes a plurality of displacer rods filled with a burnable poison gas which are inserted into the guide thimbles of the fuel assembly to displace a portion of the coolant in thus reducing the H/U ratio at the start of the cycle. The displacer rods are connected at their upper ends to a manifold which has a central opening with a plurality of inlet ports disposed about the central opening and in fluid flow communication with the rods. A rotatable valve is disposed in the central opening and operable to selectively open and close the inlet ports so as to either permit or obstruct the flow of coolant into the displacer rods in a predetermined controlled manner.

Abstract: Method for removal of radioactive cesium from a hot vapor, such as high temperature steam, including the steps of passing input hot vapor containing radioactive cesium into a bed of silicate glass particles and chemically incorporating radioactive cesium in the silicate glass particles at a temperature of at least about 700.degree. F.