Experimental molten-salt-fueled 30-Mw power reactor /

Comparison of pool-type reactor critical experiments with two-group and thirty-group calculations /

Silver, E. G.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Applied Nuclear Physics Division.

January 1958

"ORNL-2499 ; Physics and Mathematics" -c.p.Includes bibliographical references (p. 27).Operated by U...

The Unclad-Metal Breeder Reactor (UMBR) for desalting or power /

Hammond, R. P.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

January 1969

"UC-80 - Reactor Technology."--Cover.Jjanuary 1969."Includes bibliographical references.Operated by ...

Design of chemical processing plant for homogenous reactor test /

Rom, A. M.
Weeren, H. O.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Process Design Division.

January 1959

"ORNL-2784 ; Reactors-General" -c.p.Includes bibliographical references (p. 102-105).Operated by Uni...

The ORNL gas-cooled reactor : advanced concepts /

Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.
Union Carbide Corporation.

January 1958

"ORNL-2510" -c.p.Includes bibliographical references.Operated by Union Carbide CorporationMode of ac...

The ORNL gas-cooled reactor : materials and hazards /

Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.
Union Carbide Corporation.

"ORNL-2505 ; Rev." -c.p.Includes bibliographical references.Operated by Union Carbide CorporationMod...

Fabrication of the heat exchanger tube bundle for the Molten-Salt Reactor Experiment /

Donnelly, R. G.
Slaughter, G. M.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Metals and Ceramics Division.

January 1963

"ORNL-3500 ; UC-2--Metals, Ceramics, and Materials ; TID-4500 (23rd ed.)" -c.p.Includes bibliographi...

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...

Fused salt fuel processing in the ORNL volatility pilot plant /

Whitmarsh, C. L.
Carr, W. H. joint author.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory Chemical Technology Division Pilot Plant Section.

January 1960

"Date issued: May 20, 1960."At head of title: Chemical Technology Division, Pilot Plant Section.Bibl...

Activation of primary coolant in molten-salt reactor /

McGoff, D.J.
Suehrstedt, R.A.
Durrill, P.L.
Aronchick, M.P.
U.S. Atomic Energy Commission.
Massachusetts Institute of Technology. Engineering Practice School.
Massachusetts Institute of Technology. David H. Koch School of Chemical Engineering Practice
Union Carbide Nuclear Company.
Oak Ridge National Laboratory.

January 1959

"Prepared from work performed under subcontract 70 at the Oak Ridge National Laboratory with Union U...

Molten-salt reactor program quarterly progress report for periods ending ... /

Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

"Date issued: ."Description based on periods ending January 31 and April 30, 1960.Includes bibliogra...

An evaluation of the Molten Salt Breeder Reactor : prepared for the Federal Council on Science and Technology R & D Goals Study /

U.S. Atomic Energy Commission. Division of Reactor Development and Technology.
U.S. Atomic Energy Commission.

"September 1972.""UC-80."Bibliographical references: pages 53-54.Mode of access: Internet

Boron-aluminum and boron-uranium-aluminum alloys for reactor application /

Thurber, W. C.
Beaver, R. J.
Milko, J. A.
U.S. Atomic Energy Commission.
Union Carbide Nuclear Company.
Oak Ridge National Laboratory. Metallurgy Division.

January 1957

"ORNL-2149 ; Reactors--General ; TID-4500 (13th ed.)" -c.p.Includes bibliographical references (p. 2...

Steelmaking in an industrial complex /

Squires, Arthur M., 1916-
Lobo, Walter E. (Walter Eder), 1905- Acetylene production from naphtha by electric arc and by partial combustion.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

January 1968

"UC-80-Reactor technology.""ORNL-4294.""November 1968."Includes bibliographical references (p. 32).O...

Preparation and metallography of arc-melted uranium carbides /

Gray, R. J.
DuBose, C. K. H.
Thurber, W. C.
U.S. Atomic Energy Commission.
Union Carbide Nuclear Company.
Oak Ridge National Laboratory. Metallurgy Division.

January 1958

"ORNL-2446 ; Metallurgy and Ceramics" -c.p.Includes bibliographical references.Operated by Union Car...

Components of the fused-salt and sodium circuits of the aircraft reactor experiment /

McDonald, W. B. joint author.
Cobb, W. G. joint author.
Whitman, G. D. joint author.
Savage, H. W. joint author.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory Reactor Projects Division.

January 1958

"Date issued: Sep 18, 1958."At head of title: Reactor Projects Division.Includes bibliographical ref...

Comparison of pool-type reactor critical experiments with two-group and thirty-group calculations /

Silver, E. G.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Applied Nuclear Physics Division.

January 1958

"ORNL-2499 ; Physics and Mathematics" -c.p.Includes bibliographical references (p. 27).Operated by U...

The Unclad-Metal Breeder Reactor (UMBR) for desalting or power /

Hammond, R. P.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

January 1969

"UC-80 - Reactor Technology."--Cover.Jjanuary 1969."Includes bibliographical references.Operated by ...

Design of chemical processing plant for homogenous reactor test /

Rom, A. M.
Weeren, H. O.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Process Design Division.

January 1959

"ORNL-2784 ; Reactors-General" -c.p.Includes bibliographical references (p. 102-105).Operated by Uni...

The ORNL gas-cooled reactor : advanced concepts /

Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.
Union Carbide Corporation.

January 1958

"ORNL-2510" -c.p.Includes bibliographical references.Operated by Union Carbide CorporationMode of ac...

The ORNL gas-cooled reactor : materials and hazards /

Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.
Union Carbide Corporation.

"ORNL-2505 ; Rev." -c.p.Includes bibliographical references.Operated by Union Carbide CorporationMod...

Fabrication of the heat exchanger tube bundle for the Molten-Salt Reactor Experiment /

Donnelly, R. G.
Slaughter, G. M.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Metals and Ceramics Division.

January 1963

"ORNL-3500 ; UC-2--Metals, Ceramics, and Materials ; TID-4500 (23rd ed.)" -c.p.Includes bibliographi...

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...

Fused salt fuel processing in the ORNL volatility pilot plant /

Whitmarsh, C. L.
Carr, W. H. joint author.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory Chemical Technology Division Pilot Plant Section.

January 1960

"Date issued: May 20, 1960."At head of title: Chemical Technology Division, Pilot Plant Section.Bibl...

Activation of primary coolant in molten-salt reactor /

McGoff, D.J.
Suehrstedt, R.A.
Durrill, P.L.
Aronchick, M.P.
U.S. Atomic Energy Commission.
Massachusetts Institute of Technology. Engineering Practice School.
Massachusetts Institute of Technology. David H. Koch School of Chemical Engineering Practice
Union Carbide Nuclear Company.
Oak Ridge National Laboratory.

January 1959

"Prepared from work performed under subcontract 70 at the Oak Ridge National Laboratory with Union U...

Molten-salt reactor program quarterly progress report for periods ending ... /

Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

"Date issued: ."Description based on periods ending January 31 and April 30, 1960.Includes bibliogra...

An evaluation of the Molten Salt Breeder Reactor : prepared for the Federal Council on Science and Technology R & D Goals Study /

U.S. Atomic Energy Commission. Division of Reactor Development and Technology.
U.S. Atomic Energy Commission.

"September 1972.""UC-80."Bibliographical references: pages 53-54.Mode of access: Internet

Boron-aluminum and boron-uranium-aluminum alloys for reactor application /

Thurber, W. C.
Beaver, R. J.
Milko, J. A.
U.S. Atomic Energy Commission.
Union Carbide Nuclear Company.
Oak Ridge National Laboratory. Metallurgy Division.

January 1957

"ORNL-2149 ; Reactors--General ; TID-4500 (13th ed.)" -c.p.Includes bibliographical references (p. 2...

Steelmaking in an industrial complex /

Squires, Arthur M., 1916-
Lobo, Walter E. (Walter Eder), 1905- Acetylene production from naphtha by electric arc and by partial combustion.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

January 1968

"UC-80-Reactor technology.""ORNL-4294.""November 1968."Includes bibliographical references (p. 32).O...

Preparation and metallography of arc-melted uranium carbides /

Gray, R. J.
DuBose, C. K. H.
Thurber, W. C.
U.S. Atomic Energy Commission.
Union Carbide Nuclear Company.
Oak Ridge National Laboratory. Metallurgy Division.

January 1958

"ORNL-2446 ; Metallurgy and Ceramics" -c.p.Includes bibliographical references.Operated by Union Car...

Components of the fused-salt and sodium circuits of the aircraft reactor experiment /

McDonald, W. B. joint author.
Cobb, W. G. joint author.
Whitman, G. D. joint author.
Savage, H. W. joint author.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory Reactor Projects Division.

January 1958

"Date issued: Sep 18, 1958."At head of title: Reactor Projects Division.Includes bibliographical ref...

Comparison of pool-type reactor critical experiments with two-group and thirty-group calculations /

Silver, E. G.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Applied Nuclear Physics Division.

January 1958

"ORNL-2499 ; Physics and Mathematics" -c.p.Includes bibliographical references (p. 27).Operated by U...

The Unclad-Metal Breeder Reactor (UMBR) for desalting or power /

Hammond, R. P.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

January 1969

"UC-80 - Reactor Technology."--Cover.Jjanuary 1969."Includes bibliographical references.Operated by ...

Design of chemical processing plant for homogenous reactor test /

Rom, A. M.
Weeren, H. O.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Process Design Division.

January 1959

"ORNL-2784 ; Reactors-General" -c.p.Includes bibliographical references (p. 102-105).Operated by Uni...

Experimental molten-salt-fueled 30-Mw power reactor /

Abstract

Extracted data

Experimental molten-salt-fueled 30-Mw power reactor /

Abstract

Extracted data

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