A wire-activation technique for reactor-flux-profile measurements /

An indicating fluxmeter utilizing a germanium semiconductor /

Walchli, H.E.
Oak Ridge Y-12 Plant.
Carbide and Carbon Chemicals Corporation.
U.S. Atomic Energy Commission.

January 1949

"Date Issued: Jun 30 1949.""April 19, 1949."Work performed at the Carbide and Carbon Chemicals Corpo...

Liquid metal fuel reactor experiment : critical experiment - report of experimental data /

Mortenson, J. H.
Farrar, J. H.
Giesler, H. W.
Engelder, T. C.
U.S. Atomic Energy Commission.
Babcock & Wilcox Company.

January 1960

"BAW-1185.""March 1960."Includes bibliographical references (p. 73).Mode of access: Internet

Model studies of flow in the thermal-shield passages of the PWR reactor /

Flanigan, Lawrence J.
Hazard, Herbert R.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"UC-81 Reactors - Power (TID-4500, 13th Ed.).""June 26, 1957.""Report No. BMI-1198."Work performed b...

The development of a thermal-neutron-flux measuring instrument /

Fawcett, Sherwood L.
Chastain, Joel W.
Weaver, C. Vernon.
Smith, Charles K.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Physics ; (TID-4500, 11th Ed.).""April 12, 1956.""Report No. BMI-1083."Work performed by the Battel...

A traveling flux monitor for exponential piles /

Woodward, William J.
U.S. Atomic Energy Commission.
Savannah River Laboratory.
E.I. du Pont de Nemours & Company.

"Reactor Technology (TID-4500, 16th Ed.).""Printed for the United States Atomic Energy Commission Co...

Neutron flux scanner /

Bernstein, W.
Floyd, J. J.
Foster, E. H.
U.S. Atomic Energy Commission.
Brookhaven National Laboratory.

January 1951

A method of measuring the neutron flux distribution in the experimental holes through a reactor is d...

Instrumentation for studies of the exploding wire phenomenon /

Chace, W. G., author.
Cullington, E. H., author.
Air Force Cambridge Research Center (U.S.). Geophysics Research Directorate.

PB 131839."August 1957."Includes bibliographical references (pages 34-35.).Mode of access: Internet

An analysis of transients in a pressurized-water reactor during continuous rod withdrawal /

Redmond, Robert F.
Chastain, Joel W.
Stone, Joseph J.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Physics ; (TID-4500, 11th Ed.).""April 25, 1956.""Report No. BMI-1085."Includes bibliographical ref...

Studies of flow distribution in the core of a quarter-scale flow model of the PWR reactor /

Hazard, Herbert R.
Allen, John M. (John Malone), 1921-
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Engineering (TID-4500, 12th Ed.).""October 19, 1956.""Report No. BMI-1141."Work performed by the Ba...

Simulation of various accident considerations for a merchant- ship pressurized water reactor /

Stone, J. James.
Winslow, Leon E.
Byers, R. H. (Richard H.)
Gordon, B. B. (Benjamin B.)
Boyd, Roger S.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

January 1958

"August 25, 1958.""Report no. BMI-1269."Work performed by the Battelle Memorial InstituteMode of acc...

High level neutron flux monitor for reactor use /

Studley, Robert V.
U.S. Atomic Energy Commission.
Savannah River Laboratory.
E.I. du Pont de Nemours & Company.

"Instruments (TID-4500, 17th Ed.).""Printed for the United States Atomic Energy Commission Contract ...

Neutron flux measurements in the bulk shielding facility reactor /

Hill, John W.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory.

Work performed at the Oak Ridge National Laboratory under Contract No. W-7405-Eng-26."CF-51-5-164.""...

Investigation of fabrication techniques for tubular fuel elements /

Hodge, E. S.
Smith E. G.
Carlson, R. J.
Battelle Memorial Institute.
U.S. Atomic Energy Commission.
Battelle Memorial Institute, Columbus, Ohio.

January 1963

"October 28, 1963."Work performed by the Battelle Memorial InstituteMode of access: Internet

Reactor Physics Department technical activities quarterly report, April, May, June, 1967 /

Pacific Northwest Laboratory.
Dawson, Frank G., Jr., manager.
Battelle Memorial Institute. Pacific Northwest Division. issuing body.
U.S. Atomic Energy Commission.
Pacific Northwest Laboratory.

"UC-80, Ractor Technology.""January 1968."Includes bibliographical references (page 7.7).Operated by...

Critical-assembly experiments on a reflector control system for a boiling reactor /

Chastain, Joel W.
Jankowski, Francis J.
Ballowe, William C.
Wilson, Robert G.
Hogan, William S.
Dingee, David A.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Contract No. W-7405-eng-92.""UC-81 Reactors - Power (TID-4500, 13th Ed., Suppl.).""December 20, 195...

An indicating fluxmeter utilizing a germanium semiconductor /

Walchli, H.E.
Oak Ridge Y-12 Plant.
Carbide and Carbon Chemicals Corporation.
U.S. Atomic Energy Commission.

January 1949

"Date Issued: Jun 30 1949.""April 19, 1949."Work performed at the Carbide and Carbon Chemicals Corpo...

Liquid metal fuel reactor experiment : critical experiment - report of experimental data /

Mortenson, J. H.
Farrar, J. H.
Giesler, H. W.
Engelder, T. C.
U.S. Atomic Energy Commission.
Babcock & Wilcox Company.

January 1960

"BAW-1185.""March 1960."Includes bibliographical references (p. 73).Mode of access: Internet

Model studies of flow in the thermal-shield passages of the PWR reactor /

Flanigan, Lawrence J.
Hazard, Herbert R.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"UC-81 Reactors - Power (TID-4500, 13th Ed.).""June 26, 1957.""Report No. BMI-1198."Work performed b...

The development of a thermal-neutron-flux measuring instrument /

Fawcett, Sherwood L.
Chastain, Joel W.
Weaver, C. Vernon.
Smith, Charles K.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Physics ; (TID-4500, 11th Ed.).""April 12, 1956.""Report No. BMI-1083."Work performed by the Battel...

A traveling flux monitor for exponential piles /

Woodward, William J.
U.S. Atomic Energy Commission.
Savannah River Laboratory.
E.I. du Pont de Nemours & Company.

"Reactor Technology (TID-4500, 16th Ed.).""Printed for the United States Atomic Energy Commission Co...

Neutron flux scanner /

Bernstein, W.
Floyd, J. J.
Foster, E. H.
U.S. Atomic Energy Commission.
Brookhaven National Laboratory.

January 1951

A method of measuring the neutron flux distribution in the experimental holes through a reactor is d...

Instrumentation for studies of the exploding wire phenomenon /

Chace, W. G., author.
Cullington, E. H., author.
Air Force Cambridge Research Center (U.S.). Geophysics Research Directorate.

PB 131839."August 1957."Includes bibliographical references (pages 34-35.).Mode of access: Internet

An analysis of transients in a pressurized-water reactor during continuous rod withdrawal /

Redmond, Robert F.
Chastain, Joel W.
Stone, Joseph J.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Physics ; (TID-4500, 11th Ed.).""April 25, 1956.""Report No. BMI-1085."Includes bibliographical ref...

Studies of flow distribution in the core of a quarter-scale flow model of the PWR reactor /

Hazard, Herbert R.
Allen, John M. (John Malone), 1921-
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Engineering (TID-4500, 12th Ed.).""October 19, 1956.""Report No. BMI-1141."Work performed by the Ba...

Simulation of various accident considerations for a merchant- ship pressurized water reactor /

Stone, J. James.
Winslow, Leon E.
Byers, R. H. (Richard H.)
Gordon, B. B. (Benjamin B.)
Boyd, Roger S.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

January 1958

"August 25, 1958.""Report no. BMI-1269."Work performed by the Battelle Memorial InstituteMode of acc...

High level neutron flux monitor for reactor use /

Studley, Robert V.
U.S. Atomic Energy Commission.
Savannah River Laboratory.
E.I. du Pont de Nemours & Company.

"Instruments (TID-4500, 17th Ed.).""Printed for the United States Atomic Energy Commission Contract ...

Neutron flux measurements in the bulk shielding facility reactor /

Hill, John W.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory.

Work performed at the Oak Ridge National Laboratory under Contract No. W-7405-Eng-26."CF-51-5-164.""...

Investigation of fabrication techniques for tubular fuel elements /

Hodge, E. S.
Smith E. G.
Carlson, R. J.
Battelle Memorial Institute.
U.S. Atomic Energy Commission.
Battelle Memorial Institute, Columbus, Ohio.

January 1963

"October 28, 1963."Work performed by the Battelle Memorial InstituteMode of access: Internet

Reactor Physics Department technical activities quarterly report, April, May, June, 1967 /

Pacific Northwest Laboratory.
Dawson, Frank G., Jr., manager.
Battelle Memorial Institute. Pacific Northwest Division. issuing body.
U.S. Atomic Energy Commission.
Pacific Northwest Laboratory.

"UC-80, Ractor Technology.""January 1968."Includes bibliographical references (page 7.7).Operated by...

Critical-assembly experiments on a reflector control system for a boiling reactor /

Chastain, Joel W.
Jankowski, Francis J.
Ballowe, William C.
Wilson, Robert G.
Hogan, William S.
Dingee, David A.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Contract No. W-7405-eng-92.""UC-81 Reactors - Power (TID-4500, 13th Ed., Suppl.).""December 20, 195...

An indicating fluxmeter utilizing a germanium semiconductor /

Walchli, H.E.
Oak Ridge Y-12 Plant.
Carbide and Carbon Chemicals Corporation.
U.S. Atomic Energy Commission.

January 1949

"Date Issued: Jun 30 1949.""April 19, 1949."Work performed at the Carbide and Carbon Chemicals Corpo...

Liquid metal fuel reactor experiment : critical experiment - report of experimental data /

Mortenson, J. H.
Farrar, J. H.
Giesler, H. W.
Engelder, T. C.
U.S. Atomic Energy Commission.
Babcock & Wilcox Company.

January 1960

"BAW-1185.""March 1960."Includes bibliographical references (p. 73).Mode of access: Internet

Model studies of flow in the thermal-shield passages of the PWR reactor /

Flanigan, Lawrence J.
Hazard, Herbert R.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"UC-81 Reactors - Power (TID-4500, 13th Ed.).""June 26, 1957.""Report No. BMI-1198."Work performed b...

A wire-activation technique for reactor-flux-profile measurements /

Abstract

Extracted data

A wire-activation technique for reactor-flux-profile measurements /

Abstract

Extracted data

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