Investigation of the phenomena occurring within a multi-compartment containment after rupture of the primary cooling circuit in water-cooled reactors : quick look report experiment D9 /

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - March 1980 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1980

"Date published: July 1980.""NRC FIN No. A4046.""BMI-2055.""NUREG/CR-1601."Bibliography: p. 4-1.Mode...

Technical report No. 6 : containment of fragments from a runaway reactor /

White, R. W.
Botsford, N. B.
Stanford Research Institute.
U.S. Atomic Energy Commission.

"SRI Project No. GU-2164.""Contract No. AT(04-3)-115 ; Project No. 2.""UC-80, Reactor Technology--Ge...

Reactor Safety Research Programs Quarterly Report July- September 1980

Edler, S. K.

December 1980

This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from April 1 throu...

Investigation of the phenomena occurring within a multi-compartment containment after rupture of the primary cooling circuit in water-cooled reactors : project RS 50, Quick look report experiment D3 /

Battelle-Institut.
U.S. Nuclear Regulatory Commission.

January 1978

"Date published by NRC: October 1978.""Translation series.""BF RS 50 - 30 - D3.""NUREG/TR-0046."Mode...

Loss-of-coolant accident simulations in the National Research Universal Reactor /

Bennett, W. D.
Mohr, C. L.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Pacific Northwest Laboratory.

"FIN B2277.""PNL-3093.""NUREG/CR-1208.""Date published: February 1981.""Safety analysis report."Bibl...

Hydraulic studies of the lower plenum of a pressure water reactor vessel /

Weber, E.
Dittrich, W.
Germany. Bundesministerium für Forschung und Technologie.
Simens Aktiengesellschaft.

January 1977

"Translation series.""Date published by NRC: October 1977.""Original report number: BMFT-FB K 73-03....

Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials tests 1 and 2 /

Russcher, G. E.
Pacific Northwest Laboratory.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation.

"PNL-3765.""NUREG/CR-1735, Addendum 1.""NRC FIN B2277.""Date published: September 1981.""Pacific Nor...

Experimental investigation of aerosol behavior in a post-LMFBR accident reactor containment atmosphere /

Wegrzyn, J.
Shaw, D. T.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
State University of New York at Buffalo. Dept. of Electrical Engineering. Faculty of Engineering and Applied Sciences.

Prepared under contract no. AT(49-24)-0359."LAPES 78-002.""NUREG/CR-0287.""Date published: July 1978...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, June-December 1979 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1980

"Date published: June 1980.""NRC FIN No. A4046.""BMI-2064.""NUREG/CR-1555."Bibliography: p. 4-1.Mode...

Reactor containment /

Smith, Richard J.
American Society of Civil Engineers.
U.S. Atomic Energy Commission. Technical Information Service Extension

"Reactor Technology.""November, 1963."Includes bibliographical references (pages 14-15).Mode of acce...

Investigation and evaluation of cracking incidents in piping in pressurized water reactors /

U.S. Nuclear Regulatory Commission.
PWR Pipe Crack Study Group (U.S.)

January 1980

"NUREG-0691.""Date published : September 1980."Includes bibliographical references.Mode of access: I...

Markviken I : general report on the physical tests carried out in the containment chamber of the reactor /

Sonnett, A.
Tartu, H.
U.S. Nuclear Regulatory Commission.
France. Département de sûreté nucléaire.
France. Commissariat à l'énergie atomique.

January 1977

"Date published by NRC: August 1977.""Translation Series.""Rapport S.E.T.S. No. 39.""NUREG/tr-0001."...

Light-water-reactor safety research program.

Berman, M. (Marshall), 1939- author.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
Argonne National Laboratory.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.

Format not distributed to depository libraries."NUREG/CR."Mode of access: Internet.Vols. for prepar...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - June 1979 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1979

"Date published: September 1979.""NRC FIN No. A4046.""BMI-2036.""NUREG/CR-0991."Mode of access: Inte...

Technical report no. 3 : containment of fragments from runaway reactor /

Huber, G.B.
Zabel, N.R.
Stallybrass, M.P.
Keough, D.D.
Stanford Research Institute.
U.S. Atomic Energy Commission.

"UC-80, Reactors--General ; TID-4500 (15th Edition) and Supplement.""SRI Project No. GU-2164.""Octob...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - March 1980 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1980

"Date published: July 1980.""NRC FIN No. A4046.""BMI-2055.""NUREG/CR-1601."Bibliography: p. 4-1.Mode...

Technical report No. 6 : containment of fragments from a runaway reactor /

White, R. W.
Botsford, N. B.
Stanford Research Institute.
U.S. Atomic Energy Commission.

"SRI Project No. GU-2164.""Contract No. AT(04-3)-115 ; Project No. 2.""UC-80, Reactor Technology--Ge...

Reactor Safety Research Programs Quarterly Report July- September 1980

Edler, S. K.

December 1980

This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from April 1 throu...

Investigation of the phenomena occurring within a multi-compartment containment after rupture of the primary cooling circuit in water-cooled reactors : project RS 50, Quick look report experiment D3 /

Battelle-Institut.
U.S. Nuclear Regulatory Commission.

January 1978

"Date published by NRC: October 1978.""Translation series.""BF RS 50 - 30 - D3.""NUREG/TR-0046."Mode...

Loss-of-coolant accident simulations in the National Research Universal Reactor /

Bennett, W. D.
Mohr, C. L.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Pacific Northwest Laboratory.

"FIN B2277.""PNL-3093.""NUREG/CR-1208.""Date published: February 1981.""Safety analysis report."Bibl...

Hydraulic studies of the lower plenum of a pressure water reactor vessel /

Weber, E.
Dittrich, W.
Germany. Bundesministerium für Forschung und Technologie.
Simens Aktiengesellschaft.

January 1977

"Translation series.""Date published by NRC: October 1977.""Original report number: BMFT-FB K 73-03....

Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials tests 1 and 2 /

Russcher, G. E.
Pacific Northwest Laboratory.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation.

"PNL-3765.""NUREG/CR-1735, Addendum 1.""NRC FIN B2277.""Date published: September 1981.""Pacific Nor...

Experimental investigation of aerosol behavior in a post-LMFBR accident reactor containment atmosphere /

Wegrzyn, J.
Shaw, D. T.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
State University of New York at Buffalo. Dept. of Electrical Engineering. Faculty of Engineering and Applied Sciences.

Prepared under contract no. AT(49-24)-0359."LAPES 78-002.""NUREG/CR-0287.""Date published: July 1978...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, June-December 1979 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1980

"Date published: June 1980.""NRC FIN No. A4046.""BMI-2064.""NUREG/CR-1555."Bibliography: p. 4-1.Mode...

Reactor containment /

Smith, Richard J.
American Society of Civil Engineers.
U.S. Atomic Energy Commission. Technical Information Service Extension

"Reactor Technology.""November, 1963."Includes bibliographical references (pages 14-15).Mode of acce...

Investigation and evaluation of cracking incidents in piping in pressurized water reactors /

U.S. Nuclear Regulatory Commission.
PWR Pipe Crack Study Group (U.S.)

January 1980

"NUREG-0691.""Date published : September 1980."Includes bibliographical references.Mode of access: I...

Markviken I : general report on the physical tests carried out in the containment chamber of the reactor /

Sonnett, A.
Tartu, H.
U.S. Nuclear Regulatory Commission.
France. Département de sûreté nucléaire.
France. Commissariat à l'énergie atomique.

January 1977

"Date published by NRC: August 1977.""Translation Series.""Rapport S.E.T.S. No. 39.""NUREG/tr-0001."...

Light-water-reactor safety research program.

Berman, M. (Marshall), 1939- author.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
Argonne National Laboratory.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.

Format not distributed to depository libraries."NUREG/CR."Mode of access: Internet.Vols. for prepar...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - June 1979 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1979

"Date published: September 1979.""NRC FIN No. A4046.""BMI-2036.""NUREG/CR-0991."Mode of access: Inte...

Technical report no. 3 : containment of fragments from runaway reactor /

Huber, G.B.
Zabel, N.R.
Stallybrass, M.P.
Keough, D.D.
Stanford Research Institute.
U.S. Atomic Energy Commission.

"UC-80, Reactors--General ; TID-4500 (15th Edition) and Supplement.""SRI Project No. GU-2164.""Octob...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - March 1980 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1980

"Date published: July 1980.""NRC FIN No. A4046.""BMI-2055.""NUREG/CR-1601."Bibliography: p. 4-1.Mode...

Technical report No. 6 : containment of fragments from a runaway reactor /

White, R. W.
Botsford, N. B.
Stanford Research Institute.
U.S. Atomic Energy Commission.

"SRI Project No. GU-2164.""Contract No. AT(04-3)-115 ; Project No. 2.""UC-80, Reactor Technology--Ge...

Reactor Safety Research Programs Quarterly Report July- September 1980

Edler, S. K.

December 1980

This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from April 1 throu...

Investigation of the phenomena occurring within a multi-compartment containment after rupture of the primary cooling circuit in water-cooled reactors : quick look report experiment D9 /

Abstract

Extracted data

Investigation of the phenomena occurring within a multi-compartment containment after rupture of the primary cooling circuit in water-cooled reactors : quick look report experiment D9 /

Abstract

Extracted data

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