Evaluation of long term gas corrosion of heat resistant alloys for use as gas-cooled reactor fuel cladding /

Reaction of gaseous impurities in a high temperature gas-cooled reactor /

Giberson, R. C., author.
Tingey, Garth Leroy, 1932-., author.
Battelle Memorial Institute. Pacific Northwest Division. issuing body.
U.S. Atomic Energy Commission.
Pacific Northwest Laboratory.

"December 16, 1968.""UC-25, Materials."Includes bibliographical references (page 24).Operated by Bat...

A study of problems associated with release of fission products from ceramic fuels in gas-cooled reactors /

Lane, J. A.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Reactor Systems Evaluation Department.

January 1959

Includes bibliographical references (p. 71-73)."ORNL-2851 ; Reactors-Power" -c.p.Operated by Union C...

An evaluation of heating methods for thermal-rupture tests of ceramic fuel elements /

Todd, F. C.
Schofield, H. Z.
Duckworth, W. H.
Fawcett, S. L.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Subject category: Metallurgy and ceramics."--Cover."Contract No. W-7405-eng 92.""December 31, 1950....

Effects of gas corrosion and aging on ML-1 turbine alloys /

Farwell, B. E.
Brunhouse, J. S. joint author
Aerojet-General Corporation Aerojet-General Nucleonics

January 1962

"UC-25: Metals, Ceramics, and Materials"--title pageAt head of title:"Army gas-cooled reactor system...

Army gas-cooled reactor systems program : evaluation of nickel-based alloys /

Brunhouse, J. S.
Titus, G. W.
Aerojet-General Nucleonics.

January 1961

(Report of work performed in the period November 1958 - November 1959)"TID - 4500 (Sixteenth Edition...

Evaluation of alloys and coatings for use in automobile thermal reactors /

Blankenship, Charles P.
Oldrieve, Robert E.
Lewis Research Center.

January 1974

Prepared at Lewis Research Center.Cover title.Includes bibliographical references (p. 20-21).Mode of...

Summary report on materials for the GCRE-II /

Carpenter, Ray
Grosso, Anthony Del joint author
Aerojet-General Corporation Aerojet-General Nucleonics Enginnering Division.

January 1960

At head of title:"Army gas-cooled reactor systems program"UC 25: "Metallurgy and Ceramics"--title pa...

Alloys for the fusion reactor environment : a technical assessment /

United States. Division of Magnetic Fusion Energy, author.
United States. Department of Energy.

Issued January 1978.Includes bibliographical references.Mode of access: Internet

General corrosion of materials for nuclear superheat applications /

Pearl, W. L.
U.S. Atomic Energy Commission.
Vallecitos Atomic Laboratory.
General Electric Company.

January 1965

"U.S. Atomic Energy Commission Contract AT(04-3)-189, Project agreement 13.""March 1965.""GEAP-4760 ...

Corrosion of stainless steels by water boiler reactors fuels /

Busey, Harold M.
Perkins, Ralph H.
Los Alamos Scientific Laboratory.
U.S. Atomic Energy Commission.

January 1964

"Contract W-7405-ENG.36 with the U.S. Atomic Energy Commission.""LA-3101 ; UC-25, Metals, Ceramics, ...

The stress corrosion susceptibility of several alloys in hydrazine fuels /

Gilbreath, William.
Adamson, Michael J.
Ames Research Center.

January 1974

Prepared at Ames Research Center.Cover title.Includes bibliographical references (p. 13-14).Mode of ...

Washout testing of mixed oxide ceramic core fuel elements /

Hayden, K. D., author.
Battelle Memorial Institute. Pacific Northwest Division. issuing body.
U.S. Atomic Energy Commission.
Pacific Northwest Laboratory.

"UC-25, Metals, Ceramics and Materials.""October 1966."Includes bibliographical references (page 13)...

An evaluation of three oxidation-resistant alloy claddings for IN 100 and WI 52 superalloys /

Gedwill, Michael A.
United States. National Aeronautics and Space Administration.
Lewis Research Center.

Three oxidation-resistant alloy foil claddings for protecting typical gas turbine engine alloys of n...

Behavior of fuel claddings under loan and with thermal cycling in sodium /

Susskind, H.
Becker, W.
Brookhaven National Laboratory.
U.S. Atomic Energy Commission.

January 1966

Brookhaven National Laboratory [operated by] Associated Universities, Inc. under contract with the U...

Lubrication of corrosion-resistant alloys by mixtures of halogen-containing gases at temperatures up to 1200 ̊F /

Buckley, Donald H.
Johnson, Robert L. (Robert Lewis), 1929-
Lewis Research Center.

Prepared at Lewis Research Center."November 1959."Cover title.Includes bibliographical references (p...

Reaction of gaseous impurities in a high temperature gas-cooled reactor /

Giberson, R. C., author.
Tingey, Garth Leroy, 1932-., author.
Battelle Memorial Institute. Pacific Northwest Division. issuing body.
U.S. Atomic Energy Commission.
Pacific Northwest Laboratory.

"December 16, 1968.""UC-25, Materials."Includes bibliographical references (page 24).Operated by Bat...

A study of problems associated with release of fission products from ceramic fuels in gas-cooled reactors /

Lane, J. A.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Reactor Systems Evaluation Department.

January 1959

Includes bibliographical references (p. 71-73)."ORNL-2851 ; Reactors-Power" -c.p.Operated by Union C...

An evaluation of heating methods for thermal-rupture tests of ceramic fuel elements /

Todd, F. C.
Schofield, H. Z.
Duckworth, W. H.
Fawcett, S. L.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Subject category: Metallurgy and ceramics."--Cover."Contract No. W-7405-eng 92.""December 31, 1950....

Effects of gas corrosion and aging on ML-1 turbine alloys /

Farwell, B. E.
Brunhouse, J. S. joint author
Aerojet-General Corporation Aerojet-General Nucleonics

January 1962

"UC-25: Metals, Ceramics, and Materials"--title pageAt head of title:"Army gas-cooled reactor system...

Army gas-cooled reactor systems program : evaluation of nickel-based alloys /

Brunhouse, J. S.
Titus, G. W.
Aerojet-General Nucleonics.

January 1961

(Report of work performed in the period November 1958 - November 1959)"TID - 4500 (Sixteenth Edition...

Evaluation of alloys and coatings for use in automobile thermal reactors /

Blankenship, Charles P.
Oldrieve, Robert E.
Lewis Research Center.

January 1974

Prepared at Lewis Research Center.Cover title.Includes bibliographical references (p. 20-21).Mode of...

Summary report on materials for the GCRE-II /

Carpenter, Ray
Grosso, Anthony Del joint author
Aerojet-General Corporation Aerojet-General Nucleonics Enginnering Division.

January 1960

At head of title:"Army gas-cooled reactor systems program"UC 25: "Metallurgy and Ceramics"--title pa...

Alloys for the fusion reactor environment : a technical assessment /

United States. Division of Magnetic Fusion Energy, author.
United States. Department of Energy.

Issued January 1978.Includes bibliographical references.Mode of access: Internet

General corrosion of materials for nuclear superheat applications /

Pearl, W. L.
U.S. Atomic Energy Commission.
Vallecitos Atomic Laboratory.
General Electric Company.

January 1965

"U.S. Atomic Energy Commission Contract AT(04-3)-189, Project agreement 13.""March 1965.""GEAP-4760 ...

Corrosion of stainless steels by water boiler reactors fuels /

Busey, Harold M.
Perkins, Ralph H.
Los Alamos Scientific Laboratory.
U.S. Atomic Energy Commission.

January 1964

"Contract W-7405-ENG.36 with the U.S. Atomic Energy Commission.""LA-3101 ; UC-25, Metals, Ceramics, ...

The stress corrosion susceptibility of several alloys in hydrazine fuels /

Gilbreath, William.
Adamson, Michael J.
Ames Research Center.

January 1974

Prepared at Ames Research Center.Cover title.Includes bibliographical references (p. 13-14).Mode of ...

Washout testing of mixed oxide ceramic core fuel elements /

Hayden, K. D., author.
Battelle Memorial Institute. Pacific Northwest Division. issuing body.
U.S. Atomic Energy Commission.
Pacific Northwest Laboratory.

"UC-25, Metals, Ceramics and Materials.""October 1966."Includes bibliographical references (page 13)...

An evaluation of three oxidation-resistant alloy claddings for IN 100 and WI 52 superalloys /

Gedwill, Michael A.
United States. National Aeronautics and Space Administration.
Lewis Research Center.

Three oxidation-resistant alloy foil claddings for protecting typical gas turbine engine alloys of n...

Behavior of fuel claddings under loan and with thermal cycling in sodium /

Susskind, H.
Becker, W.
Brookhaven National Laboratory.
U.S. Atomic Energy Commission.

January 1966

Brookhaven National Laboratory [operated by] Associated Universities, Inc. under contract with the U...

Lubrication of corrosion-resistant alloys by mixtures of halogen-containing gases at temperatures up to 1200 ̊F /

Buckley, Donald H.
Johnson, Robert L. (Robert Lewis), 1929-
Lewis Research Center.

Prepared at Lewis Research Center."November 1959."Cover title.Includes bibliographical references (p...

Reaction of gaseous impurities in a high temperature gas-cooled reactor /

Giberson, R. C., author.
Tingey, Garth Leroy, 1932-., author.
Battelle Memorial Institute. Pacific Northwest Division. issuing body.
U.S. Atomic Energy Commission.
Pacific Northwest Laboratory.

"December 16, 1968.""UC-25, Materials."Includes bibliographical references (page 24).Operated by Bat...

A study of problems associated with release of fission products from ceramic fuels in gas-cooled reactors /

Lane, J. A.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Reactor Systems Evaluation Department.

January 1959

Includes bibliographical references (p. 71-73)."ORNL-2851 ; Reactors-Power" -c.p.Operated by Union C...

An evaluation of heating methods for thermal-rupture tests of ceramic fuel elements /

Todd, F. C.
Schofield, H. Z.
Duckworth, W. H.
Fawcett, S. L.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Subject category: Metallurgy and ceramics."--Cover."Contract No. W-7405-eng 92.""December 31, 1950....

Evaluation of long term gas corrosion of heat resistant alloys for use as gas-cooled reactor fuel cladding /

Abstract

Extracted data

Evaluation of long term gas corrosion of heat resistant alloys for use as gas-cooled reactor fuel cladding /

Abstract

Extracted data

Related items

Related items