Abstract:
An advanced gray rod control assembly (GRCA) for a nuclear reactor. The GRCA provides controlled insertion of gray rod assemblies into the reactor, thereby controlling the rate of power produced by the reactor and providing reactivity control at full power. Each gray rod assembly includes an elongated tubular member, a primary neutron-absorber disposed within the tubular member said neutron-absorber comprising an absorber material, preferably tungsten, having a 2200 m/s neutron absorption microscopic capture cross-section of from 10 to 30 barns. An internal support tube can be positioned between the primary absorber and the tubular member as a secondary absorber to enhance neutron absorption, absorber depletion, assembly weight, and assembly heat transfer characteristics.
Abstract:
A control rod guide frame comprises a self supporting stack of two or more columnar elements defining a central passage. The columnar elements may include mating features that mate at abutments between adjacent columnar elements of the stack. The control rod guide frame is suitably used in conjunction with a control rod drive mechanism (CRDM) operatively connected with at least one control rod, and a nuclear reactor core, in which the CRDM moves the at least one control rod into and out of the nuclear reactor core under guidance of the control rod guide frame. In another embodiment, a control rod guide frame comprises a stack of two or more columnar elements defining a central passage having a constant cross-section as a function of position along the central passage. In another embodiment, a control rod guide frame comprises an extruded columnar element providing continuous control rod guidance.
Abstract:
A control rod for a boiling water reactor is provided with a structure element having mutually-perpendicular four blades. The four blades have a neutron absorber-filling region that neutron absorber is held, respectively. In the structure element, a plurality of regions formed in an axial direction of the control rod include a first region having a first cross-section that forms a first united cruciform cross-section of the four blades connected one another, a second region having a second cross-section that has each separated cross-section of the four blades, and a third region having a third cross-section that has a second united cross-section of continuous two blades of the four blades, disposed in a diametrically opposite direction and facing each other and each separated cross-section of remaining two blades of the four blades, disposed perpendicularly to the continuous two blades. The first region is disposed in an upper end portion and a lower end portion of the structure element, respectively. The third region is disposed between the first regions. The second regions are disposed between the first regions exclusive of the third region.
Abstract:
A method of operating a nuclear reactor is disclosed. The reactor (1) encloses a core having a plurality of fuel rods (9). Each fuel rod (9) includes a cladding and fuel pellets of a nuclear fuel. The fuel pellets are arranged in an inner space of the cladding leaving a free volume comprising an upper plenum, a lower plenum and a pellet-cladding gap. The reactor is operated at a normal power and a normal inlet sub-cooling during a normal state. The reactor is monitored for detecting a defect on the cladding of any of the fuel rods. The operation of the reactor is changed to a particular state after detecting such a defect. The particular state permits an increase of the free volume in the defect fuel rod. The reactor is operated at the particular state during a limited time period, after which the reactor is operated at the normal state.
Abstract:
A system for exchanging a control rod drive of a nuclear reactor is provided. The system may include an integrated drive exchange assembly system (IDEAS). The IDEAS may include a trunnion cart attached to a tower assembly. The tower assembly may include an integrated extension carriage assembly.The IDEAS may also include a control rod drive adapter; and a lead cart connected to the trunnion cart assembly.
Abstract:
A reactor of a nuclear plant encloses a core having a plurality of fuel elements and a number of control rods. Each fuel element includes a plurality of fuel rods each including a cladding and nuclear fuel enclosed in an inner space of the cladding. Each control rod is insertable to and extractable from a respective position between or in respective fuel elements to influence the effect of the reactor. A method for operating the reactor includes operating the reactor at a normal effect during a normal state, monitoring the reactor for detecting a defect on the cladding of any fuel rod, reducing the effect of the reactor after the detection of a defect, operating the reactor during a particular state during a time period during which the reactor at least during a part time is operated at the reduced effect in relation to the normal effect, and extracting the inserted control rods after the time period for continuing operation of the reactor at substantially the normal state.
Abstract:
A method of producing austenite steel for use in the radiation zone of a nuclear reactor. The method comprising the steps of forming the austenite steel with about 17% by weight chromium, about 9 to 11.5% by weight nickel, about 0.04% by weight carbon, and iron impurities whose content of silicon is about 0.1% by weight and whose total content of sulfur and phosphorous is less than 0.03% by weight; and exposing the austenite steel to a temperature treatment at a temperature less than 1150 .degree. C. to produce a fine grain lattice with grain diameter features under approximately 20 .mu.m.
Abstract:
The device includes an inspection rod cluster (10) comprising a central cylindrical body (45) and a plurality of arms (46, 48) extending radially with respect to the cylindrical body (45). Guide bars (49) for the inspection rod cluster (10) in the guide elements of the guide tube may be fixed to the end of at least two arms (48), opposite the cylindrical body (45), and rotary inspection probes (47) may be fixed to the end of the other arms (46). Preferably, the probes (47) are probes for remote optical measurements by the ladar method.
Abstract:
A safety system grade dropped rod detection system for a pressurized water reactor (PWR) utilizes core exit thermocouples arranged in multiple trains and hot and cold leg RTDs to generate a safety system grade rod stop signal. The system generates from the temperature signals a relative power deviation (RD) and a curvature index (CI), which is the spatial second derivative of RD for each fuel assembly. The CI signatures not only provide rapid, reliable detection of dropped control rods, but also clearly identify failed and failing thermocouples.
Abstract:
A storage 14 of a unit 13 constituting a gang control-rod operating unit stores an A type pattern sequence for configuring an A type control rod pattern, a B type pattern sequence for configuring a B type control rod pattern, and a control rod pattern exchange sequence. The control rod pattern exchange sequence comprises groups subsequent to 5 in the A type sequence and groups subsequent to 5 in the B type sequence. A control panel includes a sequence select switch 12a, a control rod group select switch 12b, and an insert/withdraw select switch 12c. In exchanging the control rod pattern, an operator actuates the sequence select switch 12a to select the control rod pattern exchange sequence, and then actuates the control rod group select switch 12b and the insert/withdraw select switch 12c to operate a plurality of control rods at the same time for carrying out the pattern exchange. The operation of exchanging the control rod pattern is facilitated and reliability is improved. Selection of the control rod pattern exchange sequence is allowed only when reactor power is above a set value at which an RWM 17 is to be released.