Abstract: A head for closing a nuclear reactor pressure vessel shell includes an arcuate dome having an integral head flange which includes a mating surface for sealingly mating with the shell upon assembly therewith. The head flange includes an internal passage extending therethrough with a first port being disposed on the head mating surface. A vent line includes a proximal end disposed in flow communication with the head internal passage, and a distal end disposed in flow communication with the inside of the dome for channeling a fluid therethrough. The vent line is fixedly joined to the dome and is carried therewith when the head is assembled to and disassembled from the shell.

Abstract: In a field of commercial nuclear reactors, a control blade, which is inserted into and withdrawn from the core of a nuclear reactor so as to start/shut-down the operation thereof and to control the reactor power, must have soundness, high reactivity and long life. The control blade for nuclear reactors is arranged to prevent swelling of a neutron absorber so as to improve the soundness. Furthermore, even if the swelling takes place, the soundness of the control blade can be maintained. The control blade is arranged to prevent the swelling phenomenon in such a manner that boron exhibiting excellent neutron absorbing performance absorbs hydrogen which is produced as a result of reactions with the neutrons. The control blade for nuclear reactors has an upper structure member, a lower structure member, a central tie member disposed between the upper and lower structure members, a plurality of wings connected to each other by the central tie member, and neutron absorber enclosed in the wing.

Abstract: A steam generator with a heat exchanger in which the tube openings of the support plate are oversized relative to the outer diameter of the heat exchanger tubes, to facilitate assembly of the heat exchanger, and in which a positive contact preloading of the heat exchanger tubes in opposite directions is produced, once the steam generator goes to operating temperatures and pressures, by a mounting of the support plates which causes them to pull on the heat exchanger tubes in opposites directions so as to provide a passive, positive supporting of the heat exchanger tubes by the supporting plates which eliminates cross flow induced vibrations during operation, pressures despite the existence of clearance gaps between the heat exchanger tubes and the support plates through which they pass at ambient temperatures and pressures.

Abstract: A control rod driving hydraulic system of a control rod driving system of a nuclear power plant, in utilization of condensate as a control rod driving water comprises a water pressure control unit arranged for each control rod and a water pressure supply unit for commonly supplying water pressure to all control rods. The water pressure supply unit comprising a pump mechanism operatively connected to a condensate supply source for driving the control rod driving water, a filter mechanism operatively connected to the condensate supply source and the pump mechanism for filtering the condensate as the control rod driving water, a valve unit for regulating quantity of flow of the control rod driving water, and a valve unit for regulating pressure thereof. The filter mechanism including at least one hollow fiber filter unit for purifying the control rod driving water. The hollow fiber filter unit includes a backwash regeneration equipment.

Abstract: There is disclosed a nuclear reactor installation. An accumulator-type emergency core cooling system, a gravity-driven core cooling system and an equalizing system for submerging a reactor core are provided within a primary containment vessel containing a reactor pressure vessel in which the reactor core is disposed. These cooling systems are automatically operated sequentially in accordance with the pressure in the reactor pressure vessel without the need for any particular powered source. The primary containment vessel is made of steel, and the interior of this containment vessel is divided into a space containing the reactor pressure vessel and a space containing an operation floor in such a manner that the two spaces are isolated from each other.

Abstract: A grid key for interior grid cells. A rectangular main body portion is bent near the middle at approximately a 90 degree angle. Two tabs that are flush with the main body portion extend outward in opposite directions from one end and along a portion of the length of the main body portion. The opposing side of the tabs is tapered at a 45 degree angle back toward the main body portion. The main body portion has a thickened section that coincides with the tabs. The thickened section is wedged between the soft stops of an individual interior grid cell to retract the stops and allow loading of a fuel rod.

Abstract: A nuclear reactor plant is provided in which the reactor coolant system contains a dissolved solution of enriched boric acid. The boron-10 to boron-11 atomic isotope ratio of the enriched boric acid solution is greater than 30:70 at the start of the reactor core cycle. The nuclear reactor plant design provides for minimal mixing between the reactor coolant solution containing the enriched boric acid solution and the natural boric acid solution used during refueling operations.

Abstract: In combination with a nuclear power generating facility including a composite fuel pool including a reactor cavity and a spent fuel pool fluidly connectable to the reactor cavity, the composite fuel pool at least partially containing a primary fluid, a nuclear reactor vessel positioned in the reactor cavity, a residual heat removal system installed in the facility and fluidly connectable to the reactor vessel, and a spent fuel pool cooling system installed in the facility and fluidly connectable to the spent fuel pool, a temporary cooling system is provided, comprising a primary heat exchange system including a primary heat exchanger for transferring heat from a primary fluid to a secondary cooling fluid. The primary heat exchanger is temporarily locatable in the facility, and is temporarily fluidly connected to the composite fuel pool.

Abstract: A system is directed for remotely securing a canopy seal about a broken omega seal site between the control drive mechanism and the adapter tube of a nuclear reactor vessel so as to contain any radioactive leakage therebetween. The system includes a stalk measuring device for initially measuring the diameter of the adapter tube, a split canopy installation fixture which is adjusted according to the measurement detected by the stalk measuring device to position a two-piece canopy seal about the omega seal site, and a robotic weld arm for performing the upper and lower radial welds about the canopy seal as well as C-shaped vertical welds between the two-piece canopy seal.

Abstract: A nuclear reactor is joined to a steam turbine by a main steamline for discharging steam thereto. A plurality of flow control valves regulate flow to the turbine, and a bypass valve selectively bypasses a portion of the steam around the turbine to its condenser. A pressure regulator and turbine controller are operatively joined to the control valves and the bypass valve for controlling steamflow to the turbine. An apparatus for detecting failure of one of the control valves is operatively connected to the bypass valve, and upon failure of one of the control valves to channel sufficient flowrate, the bypass valve is automatically opened to reduce reactor pressure rise. The failure detecting apparatus also provides a reduction demand signal for reducing reactor power for allowing the bypass valve to close.

Abstract: Replacing regular mesh-dependent ray tracing modules in a collision/transfer probability (CTP) code with a ray tracing module based upon combinatorial geometry of a modified geometrical module (GMC) provides a general geometry transfer theory code in two dimensions (2D) for analyzing nuclear reactor design and control. The primary modification of the GMC module involves generation of a fixed inner frame and a rotating outer frame, where the inner frame contains all reactor regions of interest, e.g., part of a reactor assembly, an assembly, or several assemblies, and the outer frame, with a set of parallel equidistant rays (lines) attached to it, rotates around the inner frame.

Abstract: A part of an ICM housing including a portion to be repaired, welded to a wall of a reactor pressure vessel in operation, is cut and removed and a new ICM housing half is welded to the remaining part of the ICM housing to form a new ICM housing. The new ICM housing is provided at the welding portion thereof with a molten metal layer containing 4 wt % or more .delta. ferrite. A sleeve made of stainless steel is located at the welding portion of an inner peripheral surface of the new ICM housing made so as to be molten by a TIG welding machine to form the molten metal layer, with the molten metal layer preventing stress corrosion cracking of the new ICM housing.

Abstract: In a power station installation which is designed as a combined installation, i.e. consists of a gas turbine group (2, 3, 4, 5, 6, 8) and of a steam cycle (13, 16, 17, 18, 19, 20) downstream of the gas turbine group, the steam rate being generated in a waste heat boiler (13) by heat exchange with the exit gases from the gas turbine (5), a heat exchanger (7), which is a component of a closed cycle, with a high-temperature reactor (12) as the heat source is placed downstream of the last compressor (4) of the gas turbine group and upstream of the combustion chamber (8). In this heat exchanger (7), the compressed air undergoes vigorous caloric processing before it flows into the downstream combustion chamber (8) in which the final caloric processing of the hot gases for charging the gas turbine (5) is accomplished. The essential point here is that the pollutant emissions of any type, in particular CO.sub.

Abstract: A method of analysis of rock samples taken from the bore of a well being drilled or from the Earth's surface and performed upon the apatite grains contained within the samples. The apatite grains are separated from the surrounding rock, polished to expose internal surfaces, and etched with acid to reveal the presence and characteristics of fission tracks within the apatite to determine the geological characteristics of the apatite. The grains containing the apatite are viewed under an optical microscope or other imaging apparatus and apatite crystals or crystal fragments which contain etched fission tracks are selected for analysis. If selected for analysis, measurements may be taken to determine the size and shape of the etched pits intersecting the apatite grain surface. The measurements are taken using a digitizing apparatus interconnected to a computer and containing a point light source superimposed upon the apatite grains viewed through the microscope.

Abstract: A water storage tank in the coolant water loop of a nuclear reactor contains a tubular heat exchanger. The heat exchanger has tubesheets mounted to the tank connections so that the tubesheets and tubes may be readily inspected and repaired. Preferably, the tubes extend from the tubesheets on a square pitch and then on a rectangular pitch therebetween. Also, the heat exchanger is supported by a frame so that the tank wall is not required to support all of its weight.

Abstract: Apparatus for sealing a joint between an inclined base surface having a leak path and a mating end surface of a hollow body surrounding the leak path. Compression gasket means receive an asymmetric preload force applied through the hollow body from an environmental pressure preloading element having a variable spring constant in register with the joint. The preloading element is a ring-shaped body of a given thickness of an asymmetric radial structure defined by a plurality of unlike radially inwardly directed through slots open to its periphery and axially stacked.

Abstract: Apparatus for manipulating a vacuum hose in a reactor vessel comprises a housing with two opposing openings, an arm carried by the housing and deployable from a stowed position essentially completely within the housing to an extended position where the arm extends through the two openings in a generally horizontal position. The arm preferably has a two-fingered gripping device for gripping the vacuum hose but may carry a different end effector such as a grinding wheel. The fingers are opened and closed by one air cylinder. A second air cylinder extends the device. A third air cylinder within the housing pivotally pulls the opposing end of the arm into the housing via a pivoting member pivotally connected between the third air cylinder shaft and the arm.

Abstract: If an emergency arises in gas-cooled nuclear reactor plants having a heat exchanger for removing afterheat due to failure of a blower, the afterheat can be only inadequately removed because of the many deflections and restrictions in a primary circulation loop. In order to achieve adequate removal of afterheat solely on the basis of natural draught, a heat exchanger is located above a top reflector and reaches across a part of coolant gas bores in the top reflector. During normal operation of the nuclear reactor plant, there is a flow of cold gas through the heat exchanger in the direction toward the reactor core and in the event of an emergency, there is a flow of hot gas in a direction out of the center of the core of the reactor. A natural draught coolant circulation is established with the return of the cooled gas through the coolant gas bores in the top reflector.

Abstract: In the nuclear fuel assembly, a plurality of plate-shaped straps are assembled perpendicularly to each other into a grid shape so as to construct a supporting grid providing with a plurality of cells each of which inserts a nuclear fuel rod. A cell-size inspection device which inspects the size of each cell of the supporting grid is constructed by a base, a movable plate, a plurality of pin gauges and a sensor. The supporting grid is mounted on the base, while the movable plate is provided such that it can relatively move with respect to the base in a longitudinal direction of the cells. The pin gauges are provided on the movable plate such that they can freely slide along the longitudinal direction of the cells. When the movable plate is moved toward the supporting grid, each of the pin gauges is to be inserted into each of the cells. The sensor senses whether the pin gauge is relatively moved from the predetermined position of the movable plate.

Abstract: A sodium cooled fast ractor comprises a reactor vessel in which a liquid metal coolant is accommodated, a core disposed substantially a lower central portion of the reactor vessel in an installed state, a core support structure secured to the reactor vessel for supporting the core, the core support structure dividing an interior of the reactor vessel into a high-pressure plenum below the core and a low-pressure plenum above the high-pressure plenum, a circulation pump unit for applying a discharge pressure to the liquid metal coolant and circulating the same, and an intermediate heat exchanger for performing a heat exchanging operation of the coolant in the reactor vessel. The circulation pump unit is composed of an electromagnetic circulation pump provided with a discharge port and a closed gas space, which is filled up with a closed gas, defined above and communicated with the discharge port.