Evaluation of fuel elements having sealed anodized coatings. Final report, PT-105-621-A-67 MT

Mapping Intimacies ◽

10.2172/10152538 ◽

1958 ◽

Author(s):

R.L. Dillon

Keyword(s):

Final Report ◽

Fuel Elements

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Assembly and performance of fuel elements for H-Reactor E-N demonstration load. Final report

10.2172/10145604 ◽

1962 ◽

Author(s):

W. A. Blanton ◽

W. H. Hodgson

Keyword(s):

Final Report ◽

And Performance ◽

Fuel Elements

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Radiometallurgical examination of self supported fuel elements PT-IP-84-A. Final report

10.2172/10170446 ◽

1960 ◽

Author(s):

R. Teats

Keyword(s):

Final Report ◽

Fuel Elements

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Testing of Zircaloy-2-clad uranium seven-rod fuel elements. Final report

10.2172/10151929 ◽

1960 ◽

Author(s):

G.T. Geering

Keyword(s):

Final Report ◽

Fuel Elements

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Irradiation testing of tubular fuel elements: PT-IP 292A. Final report

10.2172/10170919 ◽

1961 ◽

Author(s):

G.T. Geering

Keyword(s):

Final Report ◽

Tubular Fuel ◽

Fuel Elements

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THERMAL STRESS TESTING OF SM-2 FUEL ELEMENTS. Final Report for January 1, 1959 to July 1, 1960

10.2172/4153294 ◽

1960 ◽

Author(s):

J.A. Christenson ◽

J.D. Kortheuer

Keyword(s):

Thermal Stress ◽

Stress Testing ◽

Final Report ◽

Fuel Elements

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Final report on program for using X-8001 aluminum alloy cladding material for Hanford fuel elements: PT-IP-43-A-84-MT, IP-80-A-91-FP and IP-2-I-99-FP

10.2172/10149999 ◽

1960 ◽

Author(s):

W.H. Hodgson

Keyword(s):

Aluminum Alloy ◽

Final Report ◽

Fuel Elements ◽

Cladding Material

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Non-nuclear performance testing SNAP 8 experimental reactor fuel elements final report

10.2172/4462590 ◽

1966 ◽

Author(s):

A.J. Fitzgerald ◽

F.A. La Scalla

Keyword(s):

Performance Testing ◽

Reactor Fuel ◽

Final Report ◽

Experimental Reactor ◽

Fuel Elements

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Final report: Irradiation performance of a coextruded, Zircaloy-2-clad three-rod cluster fuel elements, PT-IP-186-A

10.2172/10177750 ◽

1962 ◽

Author(s):

R.L. Call

Keyword(s):

Final Report ◽

Irradiation Performance ◽

Fuel Elements

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In-reactor rupture testing of Zircaloy-2-clad, coextruded fuel elements in the Engineering Test Reactor. Final report

10.2172/10162876 ◽

1962 ◽

Author(s):

R.L. Call ◽

D.C. Kaulitz

Keyword(s):

Final Report ◽

Test Reactor ◽

Fuel Elements

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Spatial distribution of fission product gamma-ray energy deposition in light water reactor fuel elements. Final report

10.2172/6874261 ◽

1978 ◽

Author(s):

R. Bass ◽

W. Johnson

Keyword(s):

Spatial Distribution ◽

Fission Product ◽

Energy Deposition ◽

Gamma Ray ◽

Reactor Fuel ◽

Light Water Reactor ◽

Final Report ◽

Light Water ◽

Water Reactor ◽

Fuel Elements

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