Abstract:
Thermal neutron absorbing composite coating materials and methods of applying such coating materials to spent nuclear fuel storage systems are provided. A composite neutron absorbing coating applied to a substrate surface includes a neutron absorbing layer overlying at least a portion of the substrate surface, and a corrosion resistant top coat layer overlying at least a portion of the neutron absorbing layer. An optional bond coat layer can be formed on the substrate surface prior to forming the neutron absorbing layer. The neutron absorbing layer can include a neutron absorbing material, such as gadolinium oxide or gadolinium phosphate, dispersed in a metal alloy matrix. The coating layers may be formed by a plasma spray process or a high velocity oxygen fuel process.
Abstract:
A catalyst system (10) has a metallic backing metal sheet coated with first and second catalytic precious metals (13, 15). This backing metal sheet has only a low mass and is a good heat conductor. It is coated in a first zone (12) with the first catalytic precious metal (13) and in a second zone (14) with the second precious metal (15). The first and second zones (12, 14) are preferably located on the same side of the backing metal sheet. Platinum and palladium are preferably used as precious metals (13, 15). Palladium is used for early ignition and platinum ensures a good activation with a sufficient resistance to catalyst poisoning.
Abstract:
An improved high energy-density battery for producing continuous low-voltage electrical energy is powered by direct conversion of the kinetic energy of charged particles to electrical potentials. An improved battery comprises at least one primary energy source (20) and a plurality of cells, each cell comprising a secondary electron emitter plate (30, 30') spaced apart from a collector plate (40, 40'). Cells are configured to maximize the number of relatively low-energy secondary electrons from the emitter plates which reaches and is retained by collector plates. Heat production is minimized during efficient energy conversion of the relatively high-energy of primary charged particles to the lower energy but relatively high current capacity of large numbers of secondary electrons. Material work functions and Fermi levels of the emitters and the collectors are chosen to favor emission of secondary electrons from emitter plates and retention of secondary electrons impinging on a collector plate, thus increasing efficiency and reducing internal battery leakage currents. Relatively low cell voltages and low heat losses in the direct conversion process mean that the energy sources may be confined in relatively small packages suitable for powering, and mounting in close proximity to, electronic microcircuits and sensors.
Abstract:
The invention relates to a container (2) in which there is a capsule (4) which contains a radioactive substance and is intended to improve the restraining capacity of the barriers formed for radioactive radiating elements (radionuclides). Said capsule is embedded in a layer (6) of zeolite and/or activated carbon.
Abstract:
A passive nuclear power plant includes a reactor vessel enclosed by a containment shell. An in-containment cooling system piped with an out-of-containment heat sink, includes an in-containment heat exchanger vertically extending adjacent the sidewall of the containment shell for inducing natural circulation of the air in the containment shell. The heat exchanger has substantially parallel water-conducting pipes with cooling fins vertically extending therefrom for transferring heat from the naturally circulating air and for condensing steam from the atmosphere.
Abstract:
The invention concerns an emergency cooling arrangement for a nuclear reactor plant, the arrangement comprising a safety container (10) housing a pressurized reactor container (2) which comprises a reactor core (3). A flood pipe (4, 4a) is provided which has an outlet opening (6, 6a) which is disposed in or on the pressurized reactor container (2) and is closed by a passively opening closure element (5, 5a). The closure element (5, 5a) opens the outlet opening (6, 6a) when a limiting temperature is exceeded. For this purpose, the closure element (5, 5a) preferably comprises a safety fuse (27) which melts at approximately 900 DEG C. The flood pipe (4, 4a) is connected to a flooding container (8) disposed geodetically above the reactor core (3), whereby coolant (11) is fed by gravity into the pressurized reactor container (2). In order to ensure that the flood pipe (4, 4a) is not triggered spuriously, it comprises outside the pressurized reactor container (2) an additional closure element (16) which closes the flood pipe (4, 4a) during normal operation and opens the flood pipe (4, 4a) in the event of a malfunction, when the temperature in the pressurized reactor container (2) increases drastically but is lower than that of the closure element (5, 5a), in particular approximately 500 DEG C. The invention further concerns a process for the emergency cooling of a reactor core (3) by means of a flood pipe (4, 4a) which is closed by a passively opening closure element (5, 5a).
Abstract:
A method for supervision of a neutron flux detector in a nuclear reactor comprising a plurality of neutron flux detectors. During a learning phase, connection weights of a neural network are determined, which network comprises at least one input layer (31) and one output layer (33). The input layer comprises a number of processing elements adapted to receive a number of input signals (S(t) - S(t-49 DELTA t)), and the output layer comprises a number of process elements adapted to deliver a number of state signals (N1, N2, N3, N4). The determination of the connection weights is done by supplying to the network a plurality of sets of input signals with known state signals, by comparing the state signals calculated by the network with the known state signals, and by successively correcting the connection weights to reduce the deviation between the known and the calculated state signals. During a supervision phase the neural network is supplied with input signals corresponding to measured values at different times from the supervised detector, and based on the connection weights determined during the learning phase, the state signals are calculated. In dependence of the calculated state signals and the state signals of a number of selected reference detectors, it is determined whether the detector is defective.
Abstract:
The invention relates to a sealing device (10) in a graphite-moderated light water-cooled nuclear reactor (1). The reactor (1) comprises a plurality of fuel channels (4) and each fuel channel (4) at its upper part encloses a plug (9). A gap (11) is provided between said fuel channel (4) and said plug (9) and sealing surfaces (12, 13) are arranged correspondingly on the inner part of the fuel channel (4) and the outer part of the plug (9), respectively. The sealing device (10) is arranged in the gap (11) between said sealing surfaces (12, 13) and is characterized in that it comprises one or more annular bodies arranged in the axial direction one after the other and making direct contact with each other. Each body is plastically deformable for transforming the force in the axial direction obtained via the plug (9) into a sealing pressure in the radial direction whereby it achieves a sealing effect of the sealing device (10). Further, the sealing device (10) is characterized in that at least that part of it, which faces the sealing surfaces (12, 13), is monolithic.
Abstract:
Impact limiters (22, 23) having noncircular outer peripheries (28, 30) are described for use to protect nuclear fuel transportation casks. The impact limiters include two different materials as impact absorbing materials. The impact limiter includes multiple sides (32, 34) and a tapered cap (30).
Abstract:
A fuel assembly for a boiling water reactor, comprises fuel rods (2), a tie plate (3), a handle device (4), and at least two water rods (7) attached to the tie plate and to the handle device. A plurality of spacers (8a, 8b), define first passages (8') for some of the fuel rods, and second passages (8") for the water rods. Each water rod comprises a tube part (7a) attached to the tie plate, and a solid part (7b) attached to the handle device. The tube part permits a flow of coolant. The spacers comprise primary spacers (8a) and a secondary spacer (8b). The primary spacers are attached to the tube parts. The tie plate, the water rods, the primary spacers and the handle device form a support structure carrying the weight of the fuel rods. The secondary spacer is positioned at the solid part of the respective water rod.