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US5502754A Expired / Lapsed US ⏱️ 0.0 years remaining

Lateral restraint for core plate of boiling water reactor

Assignee: General Electric Co
•
Filing: 1995-02-02
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Granted: 1996-03-26
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Expires: 2015-02-02
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Abstract

Abstract An apparatus for stabilizing a core plate against lateral deflection. A plurality of core plate wedge assemblies (e.g., four) are installed in the circumferential gap between the circular outer peripheral edge of the core plate and the circular cylindrical wall of the middle shell of the shroud at respective azimuthal positions. These core plate wedge assemblies are wedged into place with preload to maintain the spacing between the core plate and the shroud, thereby maintaining the alignment of the fuel assemblies. The core plate wedge assemblies further serve to transmit loads from the nuclear fuel core to the core shroud at azimuthal locations where lateral shroud restraints outside the shroud contact the reactor pressure vessel.

Inventors

  • 👤 John G. Erbes

Bibliographic Details

Application Number —
Jurisdiction US
Data Source google_patents
Last Synchronized 2026-11-08 15:20
CPC Classifications
G; G21; G21C; G21C5/00; G21C5/02; G21C5/10; F; F16; F16B; F16B39/00; F16B39/02; Y; Y02; Y02E; Y02E30/00; Y02E30/30

Claims Analysis

Total Claims: 5
Claim 1
Independent Claim 95 words
A method for stabilizing the core fuel of a light water reactor of the type having a multiplicity of fuel assemblies supported by a core plate attached along its periphery to a core shroud support ring of a shroud concentrically arranged inside a reactor pressure vessel, comprising the steps of installing first, second and third spacers between an outer circumferential surface of the core plate and an inner circumferential surface of the shroud, said first, second and third spacers being wedged with preload between said circumferential surfaces at first, second and third azimuthal positions respectively.
Claim 2
Independent Claim 95 words
A method for stabilizing the core fuel of a light water reactor of the type having a multiplicity of fuel assemblies supported by a core plate attached along its periphery to a core shroud support ring of a shroud concentrically arranged inside a reactor pressure vessel, comprising the steps of installing first, second and third spacers between an outer circumferential surface of the core plate and an inner circumferential surface of the shroud, said first, second and third spacers being wedged with preload between said circumferential surfaces at first, second and third azimuthal positions respectively.
Claim 3
Dependent Claim 48 words
The method as defined in claim 1, further comprising the steps of installing a fourth spacer between said circumferential surfaces, said fourth spacer being wedged with preload between said circumferential surfaces at a fourth azimuthal positions, said first through fourth azimuthal positions being spaced at about 90 degrees.
Claim 4
Dependent Claim 38 words
The method as defined in claim 1, wherein radial preload is applied by sliding said first spacer relative to said second spacer along a line disposed at an oblique angle relative to a centerline axis of said shroud.
Claim 5
Dependent Claim 20 words
The method as defined in claim 3, wherein said sliding occurs in response to rotation of a remotely manipulated tool.

References Cited (Backward Citations)

GB1271594A Cited
US5402570A Cited

USPTO Annuity & Maintenance Windows

Annuity Stage Window Opens Payment Deadline Surcharge Period Until Estimated Fee Status
3.5 Years (Year 4) 1999-03-26 1999-09-25 2000-03-26 $2000.00 Window Closed / Lapsed
7.5 Years (Year 8) 2003-03-26 2003-09-25 2004-03-26 $3760.00 Window Closed / Lapsed
11.5 Years (Year 12) 2007-03-26 2007-09-25 2008-03-26 $7700.00 Window Closed / Lapsed

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