General Electric Company

Westinghouse Electric Company LLC

Thanh Tu

Thomas Alfred Caine

Russell Seeman

Mark William Broaddus

Stephen K Parker

Stephen J Kaylor

Rodney Lum

John Eddes Erbes

Gerry L Hodson

Alex Nisenbaum

An improved retention apparatus includes a wedge element that is disposed between a brace element and a flow element of a nuclear reactor system. The retention apparatus further includes an engagement assembly that is engaged with the wedge element and that is structured to engage at least one of the brace element and the flow element. The engagement assembly includes a deflectable element such as a spring that is structured to apply a retention force in an engagement direction of the wedge element to resist movement of the flow element during operation of the nuclear reactor system, such as movement due to vibration.

Retention apparatus employing wedge element and engagement assembly for use in a nuclear application

In a method of monitoring deposition of a noble metal in an intergranular stress corrosion crack (IGSCC) in a metal reactor shroud wall of a nuclear reactor, a metal sample may be placed at a location within near an inner surface of the metal reactor shroud wall. The sample may be submerged below a water line in the reactor and includes at least one thermal fatigue crack. The sample is maintained at the location for a given duration, and a given amount of the noble metal is added into the reactor water while the sample is maintained at the location. The sample is then removed. In an example, a surface crevice deposition monitor for a reactor includes a flow conditioner arranged between a securing mechanism and an anchor, and at least one sample holder connected between the securing mechanism and flow conditioner.

Apparatus for monitoring deposition of a noble metal in a nuclear reactor

A vertical spring wedge restores a tight fitup against an adjacent structure, such as between an inlet mixer and an adjacent restrainer bracket in a boiling water nuclear reactor jet pump. The vertical spring wedge includes a U-shaped bracket including a pair of guiding portions and a pair of bracket holes. A pair of wedge assemblies are coupled with the bracket, each of the wedge assemblies including a wedge segment attached to a spring-loaded guide rod. The guide rods are displaceable in the bracket holes between a retracted position and an extended position. The wedge segments engage the guiding portions, and a combination of the bracket and wedge assemblies have a first width when the guide rods are in the retracted position and have a second width wider than the first width when the guide rods are in the extended position.

Vertical spring wedge

In a method of monitoring deposition of a noble metal in an intergranular stress corrosion crack (IGSCC) in a metal reactor shroud wall of a nuclear reactor, a metal sample may be placed at a location within near an inner surface of the metal reactor shroud wall. The sample may be submerged below a water line in the reactor and includes at least one thermal fatigue crack. The sample is maintained at the location for a given duration, and a given amount of the noble metal is added into the reactor water while the sample is maintained at the location. The sample is then removed. In an example, a surface crevice deposition monitor for a reactor includes a flow conditioner arranged between a top guide clamp and an anchor clamp, and at least one sample holder connected between the top guide clamp and flow conditioner.

Method of monitoring deposition of a noble metal in a nuclear reactor and deposition monitor therefor

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Hayward, CA, United States of America

Thanh Tu