Internal hydriding in irradiated defected Zircaloy fuel rods: A review (LWBR Development Program)

Mapping Intimacies ◽

10.2172/6121898 ◽

1987 ◽

Cited By ~ 1

Author(s):

J C Clayton

Keyword(s):

Development Program ◽

Fuel Rods

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LWBR development program: Flow-induced vibrational wear behavior of zircaloy clad simulated fuel rods in a grid support system

10.2172/6744550 ◽

1987 ◽

Author(s):

C. Galtz ◽

R. Stackhouse ◽

W. Campbell

Keyword(s):

Support System ◽

Wear Behavior ◽

Development Program ◽

Fuel Rods ◽

Simulated Fuel ◽

Program Flow

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Fabrication of fuel rods containing /sup 233/U pelletized oxide fuels (LWBR Development Program)

10.2172/6741692 ◽

1967 ◽

Author(s):

W.L. Frankhouser ◽

H.H. Crain ◽

R.L. Fischer ◽

J.H. Suldan ◽

J.H. Eyler ◽

...

Keyword(s):

Development Program ◽

Fuel Rods

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Topical report: fast reactor mixed carbide fuel element development program. Sodium bonded uranium plutonium carbide fuel rods irradiated to 46,000 Mwd/T

10.2172/4221648 ◽

1973 ◽

Author(s):

M. Montgomery ◽

A. Strasser ◽

J. Andersen ◽

C. Grando

Keyword(s):

Fuel Element ◽

Fast Reactor ◽

Development Program ◽

Fuel Rods ◽

Uranium Plutonium ◽

Carbide Fuel

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ROBOT3: a computer program to calculate the in-pile three-dimensional bowing of cylindrical fuel rods (AWBA Development Program)

10.2172/6663491 ◽

1982 ◽

Author(s):

S.E. Kovscek ◽

S.E. Martin

Keyword(s):

Computer Program ◽

Three Dimensional ◽

Development Program ◽

Fuel Rods

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Cladding corrosion and hydriding in irradiated defected zircaloy fuel rods (LWBR Development Program)

10.2172/5417409 ◽

1985 ◽

Author(s):

J.C. Clayton

Keyword(s):

Development Program ◽

Fuel Rods

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Irradiation testing of internally pressurized and/or graphite coated Zircaloy-4 clad fuel rods in the NRX Reactor (AWBA Development Program). [LWBR]

10.2172/6612398 ◽

1978 ◽

Author(s):

R.C. Hoffman ◽

J. Sherman

Keyword(s):

Development Program ◽

Fuel Rods

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Iodine and cesium in oxide fuel pellets and zircaloy-4 cladding of irradiated fuel rods (LWBR Development Program)

10.2172/6053164 ◽

1979 ◽

Author(s):

D.M. Ivak ◽

L.A. Waldman

Keyword(s):

Development Program ◽

Oxide Fuel ◽

Fuel Rods ◽

Fuel Pellets ◽

Irradiated Fuel

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Effect of fuel chips on cladding stress in zircaloy clad oxide fuel rods (LWBR development program)

10.2172/6179131 ◽

1978 ◽

Author(s):

J.F. Yerman

Keyword(s):

Development Program ◽

Oxide Fuel ◽

Fuel Rods

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End-of-life nondestructive examination of Light Water Breeder Reactor fuel rods (LWBR Development Program)

10.2172/5561200 ◽

1987 ◽

Author(s):

D. Gorscak ◽

W. Campbell ◽

J. Clayton

Keyword(s):

End Of Life ◽

Development Program ◽

Reactor Fuel ◽

Fuel Rods ◽

Light Water ◽

Nondestructive Examination

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End-of-life destructive examination of light water breeder reactor fuel rods (LWBR Development Program)

10.2172/5580123 ◽

1987 ◽

Cited By ~ 1

Author(s):

K.D. Richardson

Keyword(s):

End Of Life ◽

Development Program ◽

Reactor Fuel ◽

Fuel Rods ◽

Light Water

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