US3664922A
Expired / Lapsed
US
⏱️ 0.0 years remaining
In-service inspection of reactor vessel welds
Assignee: Combustion Engineering Inc
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Filing: 1969-12-18
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Granted: 1972-05-23
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Expires: 1989-12-18
Abstract
Abstract Method and apparatus for in-service inspection of nuclear reactor vessel welds. A support mechanism housing an inspection device is positioned within the reactor vessel after the internals thereof are removed. The hoist mechanism for the refueling device is then used to manipulate the inspection device from its support mechanism to the weld areas to be inspected. The inspection device includes means for remote visual and volumetric examination of the cladding and weld surfaces, respectively, as well as a displacement indicating means for determining the position of the inspection device with respect to the weld being inspected.
Inventors
- 👤 Gordon A Diwinsky
- 👤 Richard P Kosky
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-11-01 20:31
CPC Classifications
G; G21; G21C; G21C17/00; G21C17/08; G21C17/003; G21C17/01; Y; Y02; Y02E; Y02E30/00; Y02E30/30
Claims Analysis
Total Claims: 10
Claim 1
Independent Claim
110 words
In a nuclear reactor facility having a reactor vault, a pressure vessel having clad welded walls within said vault, a bridge overlying said pressure vessel, and a refueling machine mounted on said bridge for movement thereon, the improvement comprising: an in-service inspection apparatus for remotely inspecting said pressure vessel welds, the inspection apparatus including a support mechanism removable positionable within said reactor pressure vessel, and an inspection means for remote visual and volumetric cladding and weld inspection, respectively, removably housed within said support mechanism, said inspection means having an extension therefrom selectively engagable by said refueling machine for moving said inspection means from said support mechanism to an inspection position.
Claim 2
Dependent Claim
110 words
In a nuclear reactor facility having a reactor vault, a pressure vessel having clad welded walls within said vault, a bridge overlying said pressure vessel, and a refueling machine mounted on said bridge for movement thereon, the improvement comprising: an in-service inspection apparatus for remotely inspecting said pressure vessel welds, the inspection apparatus including a support mechanism removable positionable within said reactor pressure vessel, and an inspection means for remote visual and volumetric cladding and weld inspection, respectively, removably housed within said support mechanism, said inspection means having an extension therefrom selectively engagable by said refueling machine for moving said inspection means from said support mechanism to an inspection position.
Claim 3
Dependent Claim
66 words
The apparatus of claim 1 wherein said inspection means includes a remote visual inspection means, a remote volumetric inspection means, a proximity indicator for determining approach to said vessel wall in which is located the weld to be inspected, a digital displacement indicator for determining position relative to said weld being inspected, and means for maintaining said inspection means against said vessel wall during weld inspection.
Claim 4
Dependent Claim
38 words
The apparatus of claim 2 wherein said remote visual inspection means includes a TV camera means for sending a signal indicative of a visual representation of said cladding overlying said weld area being inspected to a remote monitor.
Claim 5
Dependent Claim
35 words
The apparatus of claim 2 wherein said remote volumetric inspection means includes an ultrasonic transducer crystal means for sending a signal indicative of the volumetric condition of said weld being inspected to a remote monitor.
Claim 6
Dependent Claim
54 words
The apparatus of claim 2 wherein said means for maintaining said inspection means against said vessel wall includes a slidable carriage assembly supporting said volumetric inspection means, said proximity indicator, and said digital displacement indicator, and controllable positive pressure drive units selectively biasing said carriage assembly against said pressure vessel wall during weld inspection.
Claim 7
Dependent Claim
63 words
The apparatus of claim 1 wherein said support mechanism includes a tripod fixture having three legs and appropriately shaped feet for engaging the bottom of said pressure vessel, housing means interconnecting said legs and providing a support for said inspection means, and means on said support mechanism for permitting said mechanism to be lowered and raised into and out of said pressure vessel.
Claim 8
Dependent Claim
109 words
In a nuclear reactor facility having a reactor vault, a pressure vessel having clad welded walls within said vault, a bridge overlying said pressure vessel, a refueling machine mounted on said bridge for movement thereon, and a hoist mechanism, a method for in-service inspection of the cladding and welds of said pressure vessel comprising the steps: flooding the reactor vault to prevent the escape of radioactivity, removing the internals from said pressure vessel, positioning a remote visual and volumetric inspection means within said pressure vessel in a support means, and manipulating said remote visual and volumetric inspection means by said refueling machine to accomplish said cladding and weld examination.
Claim 9
Dependent Claim
109 words
In a nuclear reactor facility having a reactor vault, a pressure vessel having clad welded walls within said vault, a bridge overlying said pressure vessel, a refueling machine mounted on said bridge for movement thereon, and a hoist mechanism, a method for in-service inspection of the cladding and welds of said pressure vessel comprising the steps: flooding the reactor vault to prevent the escape of radioactivity, removing the internals from said pressure vessel, positioning a remote visual and volumetric inspection means within said pressure vessel in a support means, and manipulating said remote visual and volumetric inspection means by said refueling machine to accomplish said cladding and weld examination.
Claim 10
Dependent Claim
80 words
The method of claim 7 wherein the step of manipulating said remote visual and volumetric inspection means includes the steps of interconnecting said refueling machine and said inspection means, removing said inspection means from its support means by said refueling machine, moving said refueling machine to move said inspection means to the weld areas to be inspected, visually and volumetrically inspecting said cladding and said welDs, respectively, and returning said inspection means to its support means by said refueling machine.
References Cited (Backward Citations)
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1975-05-23 | 1975-11-22 | 1976-05-23 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1979-05-23 | 1979-11-22 | 1980-05-23 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1983-05-23 | 1983-11-22 | 1984-05-23 | $7700.00 | Window Closed / Lapsed |