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

Two-group calculations of the critical core size of the SRE reactor /

Fillmore, F. L.
U.S. Atomic Energy Commission. Technical Information Center
North American Aviation. Atomics International Division.

January 1959

"NAA-SR-1517 (Revised) ; Physics and Mathematics.""Issued: January 15, 1959."Includes bibliographica...

Two-group calculations of the critical core size of the SRE reactor /

Fillmore, F. L.
U.S. Atomic Energy Commission. Technical Information Center
North American Aviation. Atomics International Division.

January 1956

"Issued: July 1, 1956."Includes bibliographical references (page 43).U.S. Atomic Energy Commission C...

Off-critical reactor theory /

Duane, B. H.
Selengut, D. S.
Reid, R. E.
General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division.

January 1959

"Technical Publications, Sub-Section, February 1959.""October 1956.""APEX-458. UC-34; Physics and Ma...

Radiation excursions at the ORNL critical experiments laboratory.

Thomas, J. T.
Callihan, D.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Applied Nuclear Physics Division.

January 1958

"ORNL-2452 ; Criticality Studies" -c.p.Includes bibliographical references.Operated by Union Carbide...

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...

Comparison of a fluidized-bed and an agitated-trough chemical reactor for producing ThO₂ from Th(NO₃)₄ /

Clinton, S. D.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Chemical Technology Division.

January 1960

"ORNL-2875 ; UC-4 Chemistry-General" -c.p.Includes bibliographical references (p. 19).Operated by Un...

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...

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

Alexander, L. G.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Reactor Projects Division.

January 1960

"ORNL-2796 ; UC-81--Power ; TID-4500 (15th ed.)" -c.p.Includes bibliographical references.Operated b...

Critical mass studies.

Fox, J. K.
Callihan, D.
Gilley, L. W.
U.S. Atomic Energy Commission.
Union Carbide Nuclear Company.
Oak Ridge National Laboratory. Applied Nuclear Physics Division.

January 1958

"ORNL-2367 ; Criticality Studies" -c.p.Includes bibliographical references.Operated by Union Carbide...

Chemical feasibility of homogenous neutron poisons for criticality contols in Consolidated Edison fuel processing solutions /

Moore, J. G.
Rainey, R. H.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B.

January 1960

"ORNL-2854 ; UC-10--Chemistry-Separation Processes for Plutonium and Uranium" -c.p.Includes bibliogr...

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...

Critical mass studies.

Fox, J. K.
Rohrer, E. R.
Gilley, L. W.
U.S. Atomic Energy Commission.
Union Carbide Nuclear Company.
Oak Ridge National Laboratory. Neutron Physics Division.

January 1959

"ORNL-2143 ; Criticality Studies" -c.p.Includes bibliographical references.Operated by Union Carbide...

The adequacy of scale-up in experiments on fission product behavior in reactor accidents.

Miller, C. E.
Browning, W. E.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

January 1966

UC-41 - Health and Safety"July 1966."Includes bibliographical references (p. 49-51).Operated by Unio...

The fast-neutron multiplication effect of beryllium in reactors /

H©·afele, W.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Neutron Physics Division.

January 1959

"ORNL-2779 ; Physics and Mathematics" -c.p.Includes bibliographical references.Operated by Union Car...

Two-group calculations of the critical core size of the SRE reactor /

Fillmore, F. L.
U.S. Atomic Energy Commission. Technical Information Center
North American Aviation. Atomics International Division.

January 1959

"NAA-SR-1517 (Revised) ; Physics and Mathematics.""Issued: January 15, 1959."Includes bibliographica...

Two-group calculations of the critical core size of the SRE reactor /

Fillmore, F. L.
U.S. Atomic Energy Commission. Technical Information Center
North American Aviation. Atomics International Division.

January 1956

"Issued: July 1, 1956."Includes bibliographical references (page 43).U.S. Atomic Energy Commission C...

Off-critical reactor theory /

Duane, B. H.
Selengut, D. S.
Reid, R. E.
General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division.

January 1959

"Technical Publications, Sub-Section, February 1959.""October 1956.""APEX-458. UC-34; Physics and Ma...

Radiation excursions at the ORNL critical experiments laboratory.

Thomas, J. T.
Callihan, D.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Applied Nuclear Physics Division.

January 1958

"ORNL-2452 ; Criticality Studies" -c.p.Includes bibliographical references.Operated by Union Carbide...

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...

Comparison of a fluidized-bed and an agitated-trough chemical reactor for producing ThO₂ from Th(NO₃)₄ /

Clinton, S. D.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Chemical Technology Division.

January 1960

"ORNL-2875 ; UC-4 Chemistry-General" -c.p.Includes bibliographical references (p. 19).Operated by Un...

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...

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

Alexander, L. G.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Reactor Projects Division.

January 1960

"ORNL-2796 ; UC-81--Power ; TID-4500 (15th ed.)" -c.p.Includes bibliographical references.Operated b...

Critical mass studies.

Fox, J. K.
Callihan, D.
Gilley, L. W.
U.S. Atomic Energy Commission.
Union Carbide Nuclear Company.
Oak Ridge National Laboratory. Applied Nuclear Physics Division.

January 1958

"ORNL-2367 ; Criticality Studies" -c.p.Includes bibliographical references.Operated by Union Carbide...

Chemical feasibility of homogenous neutron poisons for criticality contols in Consolidated Edison fuel processing solutions /

Moore, J. G.
Rainey, R. H.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B.

January 1960

"ORNL-2854 ; UC-10--Chemistry-Separation Processes for Plutonium and Uranium" -c.p.Includes bibliogr...

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...

Critical mass studies.

Fox, J. K.
Rohrer, E. R.
Gilley, L. W.
U.S. Atomic Energy Commission.
Union Carbide Nuclear Company.
Oak Ridge National Laboratory. Neutron Physics Division.

January 1959

"ORNL-2143 ; Criticality Studies" -c.p.Includes bibliographical references.Operated by Union Carbide...

The adequacy of scale-up in experiments on fission product behavior in reactor accidents.

Miller, C. E.
Browning, W. E.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

January 1966

UC-41 - Health and Safety"July 1966."Includes bibliographical references (p. 49-51).Operated by Unio...

The fast-neutron multiplication effect of beryllium in reactors /

H©·afele, W.
U.S. Atomic Energy Commission.
Union Carbide Corporation.
Oak Ridge National Laboratory. Neutron Physics Division.

January 1959

"ORNL-2779 ; Physics and Mathematics" -c.p.Includes bibliographical references.Operated by Union Car...

Two-group calculations of the critical core size of the SRE reactor /

Fillmore, F. L.
U.S. Atomic Energy Commission. Technical Information Center
North American Aviation. Atomics International Division.

January 1959

"NAA-SR-1517 (Revised) ; Physics and Mathematics.""Issued: January 15, 1959."Includes bibliographica...

Two-group calculations of the critical core size of the SRE reactor /

Fillmore, F. L.
U.S. Atomic Energy Commission. Technical Information Center
North American Aviation. Atomics International Division.

January 1956

"Issued: July 1, 1956."Includes bibliographical references (page 43).U.S. Atomic Energy Commission C...

Off-critical reactor theory /

Duane, B. H.
Selengut, D. S.
Reid, R. E.
General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division.

January 1959

"Technical Publications, Sub-Section, February 1959.""October 1956.""APEX-458. UC-34; Physics and Ma...

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

Abstract

Extracted data

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

Abstract

Extracted data

Related items

Related items