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

Heavy-Section Steel Technology Program Semiannual progress report, April--September 1993. Volume 10, No. 2

Pennell, W.E.

May 1995

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission...

Reference critical experiments : progress report July 1, 1978 - September 30, 1978 /

Goebel, G. R.
Rothe, R. E. (Robert E.)
Oh, I. (Inki)
United States. Department of Energy.
U.S. Nuclear Regulatory Commission. Division of Safeguards, Fuel Cycle, and Environmental Research.
Rockwell International. Rocky Flats Plant.

"RFP-2868.""NUREG/CR-0499.""NRC FIN no. A1036."Prepared for Division of Safeguards, Fuel Cycle, & En...

Heavy-section steel technology program: Semiannual progress report, October 1993--March 1994. Volume 11, No. 1

Pennell, W.E.

November 1995

The Heavy-Section Steel Technology (HSST) Program is conducted for the US Nuclear Regulatory Commiss...

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...

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...

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

Rosenfield, Alan R. author.
Zielenbach, W. J., author.
Farmelo, D. R., author.
Perrin, J. S., author.
Hoagland, R. G., author.
Marschall, C. (Charles W.), author.
Gillot, R., author.
Barnes, C. R., author.
Landow, M. P., author.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"NRC FIN no. A4046.""BMI-2036.""NUREG/CR-0991.""Date published: September 1979.""Battelle Columbus L...

Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : 4th annual report, October 1977 - October 1978 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1979."Prepared under contract no. AT(49-24)-0293."NRC FIN NO. A4046.""BMI-2025....

Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : third annual progress report, October 1976 - September 1977 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1978."Prepared under contract no. AT(49-24)-0293."BMI-1995.""NUREG/CR-0057."Inc...

Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : quarterly report, January - March 1977 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1978

"Date published: May 1978."Prepared under contract no. AT(49-24)-0293."NUREG/CR-0079."Includes bibli...

Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : quarterly report, April-June 1977 /

Hahn, G. T. author.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.

Manuscript completed October 1977, published May 1978.Prepared for Division of Reactor Safety Resear...

A critical survey on the application of plastic fracture mechanics to nuclear pressure vessels and piping /

Kanninen, Melvin F.
Broek, David.
Popelar, C. H.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1981.""NRC FIN A4046.""BMI-2080.""NUREG/CR-2110"Includes bibliographical refere...

Fatigue crack growth rates in pressure vessel and piping steels in LWR environments : final report /

Cullen, W. H.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
Materials Engineering Associates.

January 1987

"Date published: March 1987.""NRC FIN B8900.""MEA-2175.""NUREG/CR-4724."Bibliography: p. 50-54.Mode ...

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...

A study of the effects of penetration framing on steel containment buckling capacity /

Baker, William E.
Butler, Thomas A.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
Los Alamos National Laboratory.

"Date published: May 1987."Prepared under contract W-7405-ENG-36."NRC FIN No. A72222.""LA-10977-MS."...

Preliminary analysis of the effect of fatigue loading and crack propagation on crack acceptance criteria for nuclear power plant components /

Anderson, W. F.
Johns, E. C. (Earl C.)
Weidenhamer, G. H.
U.S. Nuclear Regulatory Commission. Division of Engineering Standards.

"NUREG-0726.""Date published: April 1981."Includes bibliographical references.Mode of access: Intern...

Heavy-Section Steel Technology Program Semiannual progress report, April--September 1993. Volume 10, No. 2

Pennell, W.E.

May 1995

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission...

Reference critical experiments : progress report July 1, 1978 - September 30, 1978 /

Goebel, G. R.
Rothe, R. E. (Robert E.)
Oh, I. (Inki)
United States. Department of Energy.
U.S. Nuclear Regulatory Commission. Division of Safeguards, Fuel Cycle, and Environmental Research.
Rockwell International. Rocky Flats Plant.

"RFP-2868.""NUREG/CR-0499.""NRC FIN no. A1036."Prepared for Division of Safeguards, Fuel Cycle, & En...

Heavy-section steel technology program: Semiannual progress report, October 1993--March 1994. Volume 11, No. 1

Pennell, W.E.

November 1995

The Heavy-Section Steel Technology (HSST) Program is conducted for the US Nuclear Regulatory Commiss...

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...

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...

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

Rosenfield, Alan R. author.
Zielenbach, W. J., author.
Farmelo, D. R., author.
Perrin, J. S., author.
Hoagland, R. G., author.
Marschall, C. (Charles W.), author.
Gillot, R., author.
Barnes, C. R., author.
Landow, M. P., author.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"NRC FIN no. A4046.""BMI-2036.""NUREG/CR-0991.""Date published: September 1979.""Battelle Columbus L...

Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : 4th annual report, October 1977 - October 1978 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1979."Prepared under contract no. AT(49-24)-0293."NRC FIN NO. A4046.""BMI-2025....

Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : third annual progress report, October 1976 - September 1977 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1978."Prepared under contract no. AT(49-24)-0293."BMI-1995.""NUREG/CR-0057."Inc...

Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : quarterly report, January - March 1977 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1978

"Date published: May 1978."Prepared under contract no. AT(49-24)-0293."NUREG/CR-0079."Includes bibli...

Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : quarterly report, April-June 1977 /

Hahn, G. T. author.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.

Manuscript completed October 1977, published May 1978.Prepared for Division of Reactor Safety Resear...

A critical survey on the application of plastic fracture mechanics to nuclear pressure vessels and piping /

Kanninen, Melvin F.
Broek, David.
Popelar, C. H.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1981.""NRC FIN A4046.""BMI-2080.""NUREG/CR-2110"Includes bibliographical refere...

Fatigue crack growth rates in pressure vessel and piping steels in LWR environments : final report /

Cullen, W. H.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
Materials Engineering Associates.

January 1987

"Date published: March 1987.""NRC FIN B8900.""MEA-2175.""NUREG/CR-4724."Bibliography: p. 50-54.Mode ...

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...

A study of the effects of penetration framing on steel containment buckling capacity /

Baker, William E.
Butler, Thomas A.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
Los Alamos National Laboratory.

"Date published: May 1987."Prepared under contract W-7405-ENG-36."NRC FIN No. A72222.""LA-10977-MS."...

Preliminary analysis of the effect of fatigue loading and crack propagation on crack acceptance criteria for nuclear power plant components /

Anderson, W. F.
Johns, E. C. (Earl C.)
Weidenhamer, G. H.
U.S. Nuclear Regulatory Commission. Division of Engineering Standards.

"NUREG-0726.""Date published: April 1981."Includes bibliographical references.Mode of access: Intern...

Heavy-Section Steel Technology Program Semiannual progress report, April--September 1993. Volume 10, No. 2

Pennell, W.E.

May 1995

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission...

Reference critical experiments : progress report July 1, 1978 - September 30, 1978 /

Goebel, G. R.
Rothe, R. E. (Robert E.)
Oh, I. (Inki)
United States. Department of Energy.
U.S. Nuclear Regulatory Commission. Division of Safeguards, Fuel Cycle, and Environmental Research.
Rockwell International. Rocky Flats Plant.

"RFP-2868.""NUREG/CR-0499.""NRC FIN no. A1036."Prepared for Division of Safeguards, Fuel Cycle, & En...

Heavy-section steel technology program: Semiannual progress report, October 1993--March 1994. Volume 11, No. 1

Pennell, W.E.

November 1995

The Heavy-Section Steel Technology (HSST) Program is conducted for the US Nuclear Regulatory Commiss...

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

Abstract

Extracted data

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

Abstract

Extracted data

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