Apparatus and method for inspecting areas surrounding nuclear boiling water reactor core and annulus regions
First Claim
1. An apparatus for inspecting the core and annulus regions of nuclear boiling water reactors, the apparatus comprising:
- a carriage assembly containing electrical control wiring;
a propulsion system for propelling the apparatus, the propulsion system being mounted on the underside of the carriage assembly, wherein the propulsion system comprises a spring-loaded drive assembly having a plurality of rollers adapted to rest on top of the reactor steam dam, a pinch-roller assembly having a spring-clamp tensioning a plurality of pinch-rollers positioned in a plane perpendicular to that of the plurality of rollers adapted to rest on top of the reactor steam dam, a drive mechanism for forward and reverse movement of the apparatus, wherein the drive mechanism powers a plurality of driver rollers positioned opposite to the pinch-rollers;
at least one turret-type assembly located on the carriage assembly for mounting and pivoting at least one extendable telescoping mast assembly, the at least one mast assembly being capable of extending a predetermined distance above and below the carriage assembly, the at least one mast assembly supporting at least one piece of inspection and maintenance equipment; and
a control mechanism for controlling the movement, inspection and maintenance attributes of the apparatus, the control mechanism being capable of being operated from a location remote from the apparatus.
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Accused Products
Abstract
A remotely controlled apparatus (112) for inspecting the core (102) and annulus (104) areas of nuclear boiling water reactors (100) includes a circumferential drive mechanism for propelling the apparatus (112) on the steam dam (108) of the reactor (100). The inspection apparatus (112) uses a set of driver rollers (314) that grip the side of the steam dam (108) and provide propulsion for the apparatus. A pinch-roller assembly with high-tension springs (308) and pneumatic air cylinders (310) is utilized for removably securing a set of pinch rollers (312) to the side of the steam dam opposite the side of the driver rollers (314). A set of rollers (304) are adapted to rest on top of the steam dam (108), supporting the weight of the apparatus (112) and enabling the apparatus to move around the steam dam (108). Two positioning guide rails (306) aid in the balance of the apparatus (112), especially when it is stationary. The apparatus (112) has a watertight main body (202), which houses the electrical control wiring and circuitry. The main body (202) has a front camera (204) and a rear camera (205) used to direct the movements of the apparatus (112). The main body also has two turret-type telescoping mast assemblies (208) with telescoping masts 210 and 212, which are capable of extending at a selected distance above and below the main body (202). The mast assemblies 210 and 212 support inspection equipment such as radiation-shielded EVT-1-capable video cameras and radiation-tolerant fiberscopes. The apparatus (112) and its inspection tools are remotely controlled via control consoles with video monitors from a low-dose, non-contaminated enclosure located remotely from a boiling water reactor.
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Citations
29 Claims
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1. An apparatus for inspecting the core and annulus regions of nuclear boiling water reactors, the apparatus comprising:
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a carriage assembly containing electrical control wiring;
a propulsion system for propelling the apparatus, the propulsion system being mounted on the underside of the carriage assembly, wherein the propulsion system comprises a spring-loaded drive assembly having a plurality of rollers adapted to rest on top of the reactor steam dam, a pinch-roller assembly having a spring-clamp tensioning a plurality of pinch-rollers positioned in a plane perpendicular to that of the plurality of rollers adapted to rest on top of the reactor steam dam, a drive mechanism for forward and reverse movement of the apparatus, wherein the drive mechanism powers a plurality of driver rollers positioned opposite to the pinch-rollers;
at least one turret-type assembly located on the carriage assembly for mounting and pivoting at least one extendable telescoping mast assembly, the at least one mast assembly being capable of extending a predetermined distance above and below the carriage assembly, the at least one mast assembly supporting at least one piece of inspection and maintenance equipment; and
a control mechanism for controlling the movement, inspection and maintenance attributes of the apparatus, the control mechanism being capable of being operated from a location remote from the apparatus. - View Dependent Claims (2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 19, 20, 21, 22, 23, 24, 25, 26)
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27. An apparatus for inspecting and maintaining in-vessel and annulus areas of boiling water reactors in nuclear power plants, the apparatus comprising;
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a means for engaging the apparatus onto a boiling water reactor steam dam;
a propulsion means for propelling the apparatus along the steam dam;
at least one of an inspection and maintenance means mounted onto the apparatus; and
a control means for controlling the means for engaging, the propulsion means, and the at least one of the inspection and maintenance means.
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28. An apparatus for inspecting and maintaining boiling water reactors in nuclear power plants, wherein the apparatus locates and navigates on a steam dam of a reactor core shroud, the apparatus comprising;
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a watertight carriage assembly, the carriage assembly containing electrical control wiring and at least one video camera;
a propulsion system for propelling the apparatus, the propulsion system being mounted on the underside of the carriage assembly, wherein the propulsion system comprises a plurality of rollers adapted to rest on top of the reactor steam dam, a pinch-roller assembly having a spring-clamp and a pneumatic air cylinder tensioning a plurality of pinch-rollers positioned in a plane perpendicular to that of the plurality of rollers adapted to rest on top of the reactor steam dam, a drive mechanism for forward and reverse movement of the apparatus, wherein the drive mechanism powers a plurality of driver rollers positioned opposite the pinch-rollers with the aid of circumferential drive electrical motors;
at least one guide rail attached to the underside of the carriage assembly for positioning and stabilizing the apparatus on the reactor steam dam;
at least one turret-type assembly for mounting and pivoting at least one telescoping mast assembly, the at least one telescoping mast assembly being capable of extending at a selected distance above and below the carriage assembly, wherein the at least one mast assembly includes at least one piece of inspection equipment, the inspection equipment comprising at least one of a fiberscope composed of radiation-tolerant quartz, a tungsten-shielded video camera, the cameras having controllable focus and zoom adjustment settings, and a rotational right-angle camera with image rotation compensation; and
a control mechanism for remotely controlling the propulsion system, the at least one turret-type assembly, the at least one telescoping mast assembly, and the at least one piece of inspection equipment, the control mechanism comprising at least one console.
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29. A mechanism for propelling and positioning equipment on a boiling water reactor steam dam, the mechanism comprising;
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a drive mechanism for forward and reverse movement of the equipment along the steam dam, the drive mechanism including at least one motor for providing power to propel the apparatus;
a drive wheel assembly having a plurality of driver rollers attached to the at least one motor, wherein the driver rollers grip the side of the steam dam;
a pinch-roller assembly having a high-tension spring with a pneumatic air assist for movably securing a plurality of pinch rollers, wherein the pinch-rollers grip the side of the steam dam opposite the side of the driver rollers; and
a plurality of wheels adapted to rest on top of the steam dam.
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Specification