1. Field of the Invention
The present application is generally drawn to Boiling Water Reactor (BWR) work platforms and more particularly to portable multi function work platforms adjustably installable over the reactor cavity of different reactors during refueling of the reactors.
2. Description of the Prior Art
Much of the maintenance performed in nuclear power plants is similar to that for conventional non-nuclear systems. This includes equipment lubrication, fluid level checks, adjustments, and in-service inspections. Because most of the active systems are fluid (water, steam or air) systems, most of the work is performed on pumps, valves, fans and filters. In addition, the electrical distribution systems and the instrument and control (IC) systems require regularly scheduled maintenance. As previously discussed, nuclear systems are unique in that many components are inaccessible.
The reactor vessel and its internals are static components requiring little maintenance. Activities that are performed during each refueling outage focus on the integrity of the reactor vessel. During refueling, the reactor vessel head must be removed from the reactor vessel to gain access to the core. When this is done some of the irradiated fuel assemblies are removed and replaced with new fuel assemblies, while the other fuel assemblies are reshuffled within the reactor core. This is also the time when the various vessel components are inspected for wear and defects. The process of fuel movement and vessel inspection was done in series in previous outages.
A work platform is assembled and installed prior to this fuel movement process and is used for the mentioned inspection functions. Various such inspection platforms or decks are known and some are described in the following US patents.
U.S. Pat. No. 5,102,612 provides a permanent deck structure or platform that is outside of the reactor cavity and allows remote access to the reactor annulus for inspection and repair if necessary.
U.S. Pat. No. 5,359,632 provides an annular plate around the outside of the reactor with inner and outer support rings with access ports therein. Thus inspection is done remotely to the cavity.
U.S. Pat. No. 5,295,167 provides an auxiliary refueling bridge work platform mounted on a rigid frame adjacent to the work station. The platform is attached to a movable platform crane which is positioned to allow the use of the platform. As such this platform can not be used during refueling.
In view of the above known platforms it will be seen that a portable and easily assembled work platform which could be adjustably installed inside the reactor cavity of various reactors and could be used simultaneously with the refueling operation to allow inspection and repair of the reactor vessel from the upper cavity region was sorely needed.
The present invention solves the mentioned problems of the prior work platforms and others by providing a multi section work platform capable of being mounted in various BWRs utilizing sections that are easily transported in sea-land containers and installed into the reactor cavity of various BWRs having differing refueling floor configurations. The platform is supported by the refuel floor and provides sufficient head room for personnel to provide simultaneous inspection and repair of the reactor during the movement of the individual fuel assemblies during the refueling process.
The work platform is easily assembled from the plurality of sections into an annular ring having a plurality of baskets allowing workers to be on the platform to provide inspection and repair functions. The assembled platform also has an opening therein for fuel movement during the inspection work process. The platform is supported by a plurality of adjustable legs or outriggers which adjust both laterally and radially to clear various critical refuel floor obstructions such as service pits which allows for adaptation to various refuel floor configurations.
In view of the above it will be seen that one aspect of the present invention is to provide a reactor refueling work platform which is situated inside the reactor cavity to allow simultaneous inspection/repair of the reactor during fuel movement activities.
Another aspect of the present invention is to provide a portable work platform which is formed from a plurality of sections and is easily assembled and installed into the reactor cavity to allow local inspection/repair of the reactor.
Yet another aspect is to provide a portable work platform having a plurality of assembled sections which is easily disassembled and each section shipped to another reactor location in its own designated sea-land container.
Still yet another aspect is to provide a portable work platform having a plurality of adjustable legs for supporting the platform on various reactor refueling floor configurations.
Still yet another aspect is to provide a portable work platform having a plurality of adjustable legs which extend longitudinally as well as rotating radially to avoid refueling floor obstructions which allows for adaptation to various refuel floor configurations.
These and other aspects of the present invention will be more fully understood after a perusal of the following description of the preferred embodiment, when considered along with the accompanying drawings.
In the drawings wherein:
Referring now to the drawings generally and
In order to reduce refueling outage durations, utilities that operate Boiling Water Reactors (BWRs) are reviewing all outage tasks/processes to identify areas where critical path duration reductions can be attained. One such task is the performance of the In-Vessel Visual Inspections, which requires approximately 72 hours. Current in-vessel inspection methods result in recurring interferences with fuel off-load and re-load efforts. As a result, the RCWP (10) is designed to facilitate inspections without impeding refueling activities, is capable of adapting to various reactors and refuel floor configurations via adjustable structural support leg assemblies (12) or outriggers. The RCWP is easily transportable over-the-road using four sea-land containers. This is possible since the RCWP is comprised of three main structures (12, 14, 16) which are integral in allowing this structure to be versatile and adjustable to various reactor and refuel floor configurations. These three items are listed below:
The above mentioned items identified comprise four separate section assemblies (18, 20, 22, 24) and are shipped to the site in four (4) 20′×8′×10′ Sea-Land containers. In addition to the items identified above, a jib crane, a spreader beam assembly (26), an access platform (28), access ladder (30), and necessary rigging are all packaged and shipped in four sea-land containers.
The outrigger assemblies (12) are used to provide the necessary support for the RCWP once it is installed above the applicable reactor vessel (RV). The RCWP utilizes eight (8) of these outrigger assemblies (12), which have been designed to be the most versatile feature on the RCWP. As best seen in
Referring back to
The RCWP has four (4) basket assemblies (16) used for work activities, which provides 330-degrees of circumferential access to the reactor with the remaining 30-degrees allowing movement of fuel from the reactor vessel to the fuel storage pool. Each basket assembly (16) is constructed of stainless steel and is equipped with handrails (64). Additionally, each basket assembly is equipped with both electrical service and compressed air supply for in-vessel inspection equipment. All electrical and air systems onboard the RCWP require a connection to the applicable plant service supply on the Refuel Floor.
The access platform (28) is utilized to provide a walkway from the refuel floor to the RCWP. This separate structure is installed after the RCWP has been placed in the cavity. This access platform (28) relies on the refuel floor and the RCWP basket handrails (64) for support.
The outrigger assemblies (12) are adjustable such that these structural support members (arm assemblies (38)) can be positioned by telescoping and rotating to miss critical areas in the refuel cavity and/or reactor floor (68) as see in
Additionally, depending on the available refuel floor space (68), it may be necessary to assemble the four sections of the RCWP and rotate or tuck the outrigger arm assemblies (38) inward to reduce the amount of floor space taken up prior to installing this structure as is best seen in
As discussed earlier, the RCWP has been designed such that it can be disassembled, packaged in four sea-land containers (70), and shipped over-the-road to the next BWR utility site. As depicted in
It will be understood that certain details, obvious modifications and applications have been deleted herein for the sake of conciseness and readability but are fully intended to fall within the scope of the following claims.
Number | Date | Country | |
---|---|---|---|
60571468 | May 2004 | US |