Abstract:
A vent tube (66) and housing nut (62) replace the original housing plug (52) on a pressurized water nuclear reactor. The vent tube engages the installed vent stem (38) cross-slot (48) with a cross-shaped projection (70). During operation, the vent tube (66) is pushed down to engage the vent stem (38) and rotated to allow vented air to travel through stem (38) and tube (66). After venting, the vent stem is rotated back and tightened. The invention provides visual indication of a leaking ball (32) since any leakage lifts vent tube (66). Time required for venting is reduced and no removal of installed ball seal (32, 34), a proven primary seal, is required.
Abstract:
An apparatus for monitoring the position of the shaft (1) of a coolant circulating pump of a nuclear steam generating system comprising light source (3) for directing a light beam at a number of reflecting surfaces (5a) on the shaft (1) and a pair of spaced apart light receiving devices (7) adapted to receive light beams reflected off the reflecting surface (5). Light from the receiving devices (7) is conveyed, by fiber optic cables (9), to intensity measuring devices (11) which measure the intensity of the two light beams on a time-dependent basis. A processor (13) calculates the shaft rotational speed and the magnitude of the shaft wobble as functions of the time-dependent intensity measurements of the pair of reflected light beams.
Abstract:
Valve leakage is quantified by measuring a variable that is commensurate with a heat transfer characteristic of the pipe wall (30) and comparing the measurements to data stored in a database (84) which embodies a quantitative relationship between an index commensurate with the heat transfer characteristic variable and a range of valve leakage rates that could occur for the given value. In a straight forward implementation of the invention, a thermal hydraulic analysis of the specific valve and associated piping are performed a priori to establish a database of pipe wall temperature downstream of the valve as a function of steam flow rate. The wall temperature is simply measured and compared with the database. In another embodiement, an air cooled sleeve (54) is installed around the pipe (48) downstream of the valve (50) and a controlled flow of air is passed through the annulus (62) between the pipe and the sleeve. The temperature rise of the flowing air is measured and is used to compute the flow rate of steam leaking through the valve. In yet another embodiment, the valve leakage is quantified by monitoring and controlling heat input into a local section of a horizontal pipe (94) upstream of the valve. The center zone (106) of the heaters (96) is controlled to raise the pipe temperature a certain amount above the steam temperature and the power required to maintain the temperature is measured. The database provides a quantitative relationship between such power input and stream flow through the valve.
Abstract:
A mechanical spring journal assembly (20) particularly suited for use in a bowl mill (10) of the type that is employed for purposes of effectuating therewithin the pulverization of material such as coal. It is through the operation of the subject mechanical spring journal assembly (20) that there is established the magnitude of the forces which the grinding rolls (18) of the bowl mill (10) apply to the coal for purposes of accomplishing the pulverization of the coal. The subject mechanical spring journal assembly (20) includes spring housing means (44) comprising a self-contained subassembly unit for the operating components of the mechanical spring journal assembly (20), stud bearing means (38) attached to one end of the spring housing means (44), preload stud means (40) having one end thereof supported by the stud bearing means (38), pressure spring means (42) positioned in surrounding relation to the preload stud means (40) and adjustment means (46) operative for mounting the mechanical spring journal assembly (20) in the bowl mill (10).
Abstract:
The system (10) is particularly suited for reclaiming used foundry sand by means of thermal reclamation. The used sand, which preferably is first fed through a lump-crusher, shake-out apparatus (12), is made to pass through thermal reclaimer means (14) while being heated to a predetermined temperature for a preestablished period of time in order to accomplish the burning away of the organic materials, i.e., matter, which are present in the used sand. From the thermal reclaimer means (14), the used sand passes to and through the post reclaimer means (15) for further reclaiming and then to and through the primary cooling means (16) wherein the heated sand is cooled to a suitable temperature. The separator means (18) is operative to effect the removal of tramp metal from the cooled, thermally reclaimed sand. Thereafter, the cooled, thermally reclaimed sand is made to pass through the classifying and dust removal means (19) for classifying and removal of dust and fines and then through the scrubber means (20) wherein the dust associated with the particles of sand is removed therefrom. Finally, the substantially dust-free, cooled, thermally reclaimed sand passes through the secondary cooling means (22) wherein the sand is further cooled to substantially ambient temperature.
Abstract:
A control scheme for large circulating fluidized bed steam generators (CFB) (2) wherein direct control is effected therewith over the temperature of the large circulating fluidized bed steam generators (CFB) (2) and wherein independent control (70, 72, 28a, 30a, 32a, 34, 36), (74, 28b, 30b, 32b, 34, 36) is effected therewith over the final superheat steam temperature of the large circulating fluidized bed steam generators (CFB) (2) as well as over the final reheat steam temperature of the large circulating fluidized bed steam generators (CFB) (2).
Abstract:
A fluidized bed combustion system (10) particularly suited for use to effect the incineration, i.e., combustion therewith of wood waste/sludge mixtures that have high moisture and ash content which makes them difficult to burn. The fluidized bed combustion system (10) includes a fluidized bed combustor (12) embodying a fluidized bed (24) composed of bed solids. Air is injected into the fluidized bed (24) through an air distributor (28) to establish a first controlled fluidizing velocity zone and a second controlled fluidizing velocity zone therewithin. Material (42b) is introduced into the fluidized bed combustor (12) above the second controlled fluidizing velocity zone. Bed solids are projected from the first controlled fludizing velocity zone to the second controlled fluidizing velocity zone whereupon the bed solids rain down upon the material (42b) and effect a covering thereof. The material (42b) is then dried and thereafter combusted. Inerts/tramp materials/clinkers as well as large diameter solids entrained with the material (42b) are segregated therefrom and then are removed (64) from the fluidized bed combustor (12).
Abstract:
A system (10) and method (42, 44, 46, 48, 52, 54) for generating an index (38, 132, 40, 134) commensurate with the degree to which a tube array degrades over a period of time due to corrosion in a particular operating environment. A data array (62, 114) is created defining the number of tubes in the tube array, a plurality of time points defining time intervals during which the degradation is to be assessed, and operating conditions that induce corrosion during each time interval. The expected degradation value of the array is computed over each of a plurality of time points using a deterministic failure model (88) having at least one parameter (102, 104, 106) that is assumed constant at each time point. For each time point and at least one parameter, a plurality of values of the parameter (108, 110) that deviate from the assumed constant value, are generated. For each time point, a plurality of degradation values are computed using the deterministic model with each of the plurality of deviated values of the parameter, thereby defining a distribution (34) of degradation values at the time point surrounding the expected degradation value (36, 130) at the time point. An index (38, 132, 40, 134) is generated from the distribution of values, commensurate with the uncertainty at each time point, in the expected degradation value (36, 130) as computed by the deterministic model.
Abstract:
A permanent annular ring seal and refueling deck assembly providing an effective water barrier over the annular space between a nuclear reactor vessel flange and a surrounding annular ledge includes annular platform, a support and a joint seal. The joint seal has an upper cylindrical section and a lower flexible coil or arcuate shaped section which provides for greater accommodation of vessel radial, axial and rotational movements, and reduces joint stress.