Explore: Embrittlement
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Source: The Open Library
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1Embrittlement by liquid metals
By M. H. Kamdar
“Embrittlement by liquid metals” Metadata:
- Title: Embrittlement by liquid metals
- Author: M. H. Kamdar
- Language: English
- Number of Pages: Median: 374
- Publisher: Pergamon Press
- Publish Date: 1973
- Publish Location: Oxford - New York
“Embrittlement by liquid metals” Subjects and Themes:
- Subjects: Embrittlement - Liquid metals - Metals - Brittleness
Edition Identifiers:
- The Open Library ID: OL5463578M
- Online Computer Library Center (OCLC) ID: 699355
- Library of Congress Control Number (LCCN): 73166252
- All ISBNs: 9780080171326 - 008017132X
Access and General Info:
- First Year Published: 1973
- Is Full Text Available: Yes
- Is The Book Public: No
- Access Status: Borrowable
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2Small specimen test techniques
By E. van Walle
“Small specimen test techniques” Metadata:
- Title: Small specimen test techniques
- Author: E. van Walle
- Language: English
- Number of Pages: Median: 626
- Publisher: ASTM
- Publish Date: 1998
- Publish Location: West Conshohocken, PA
“Small specimen test techniques” Subjects and Themes:
- Subjects: ➤ Notched bar testing - Materials - Congresses - Embrittlement - Light water reactors - Testing - Metals
Edition Identifiers:
- The Open Library ID: OL365361M
- Library of Congress Control Number (LCCN): 98025686
- All ISBNs: 0803124767 - 9780803124769
Access and General Info:
- First Year Published: 1998
- Is Full Text Available: Yes
- Is The Book Public: No
- Access Status: Borrowable
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3Radiation embrittlement of nuclear reactor pressure vessel steels
By L. E. Steele
“Radiation embrittlement of nuclear reactor pressure vessel steels” Metadata:
- Title: ➤ Radiation embrittlement of nuclear reactor pressure vessel steels
- Author: L. E. Steele
- Language: English
- Number of Pages: Median: 300
- Publisher: ASTM - Astm Intl
- Publish Date: 1986
- Publish Location: Philadelphia, PA
“Radiation embrittlement of nuclear reactor pressure vessel steels” Subjects and Themes:
- Subjects: Steel - Congresses - Effect of radiation on - Nuclear pressure vessels - Embrittlement
Edition Identifiers:
- The Open Library ID: OL2717616M
- Online Computer Library Center (OCLC) ID: 13644269
- Library of Congress Control Number (LCCN): 86010811
- All ISBNs: 0803104731 - 9780803104730
Access and General Info:
- First Year Published: 1986
- Is Full Text Available: Yes
- Is The Book Public: No
- Access Status: Borrowable
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4Temper embrittlement in steel
By Symposium on Temper Embrittlement in Steel Philadelphia 1967.
“Temper embrittlement in steel” Metadata:
- Title: Temper embrittlement in steel
- Author: ➤ Symposium on Temper Embrittlement in Steel Philadelphia 1967.
- Language: English
- Number of Pages: Median: 250
- Publisher: ➤ American Society for Testing and Materials
- Publish Date: 1968
- Publish Location: Philadelphia
“Temper embrittlement in steel” Subjects and Themes:
- Subjects: Addresses, essays, lectures - Embrittlement - Heat treatment - Steel
Edition Identifiers:
- The Open Library ID: OL5612031M
- Online Computer Library Center (OCLC) ID: 441216
- Library of Congress Control Number (LCCN): 68019914
Access and General Info:
- First Year Published: 1968
- Is Full Text Available: Yes
- Is The Book Public: No
- Access Status: Borrowable
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5Long-term embrittlement of cast duplex stainless steels in LWR systems
By O. K. Chopra
“Long-term embrittlement of cast duplex stainless steels in LWR systems” Metadata:
- Title: ➤ Long-term embrittlement of cast duplex stainless steels in LWR systems
- Author: O. K. Chopra
- Language: English
- Publisher: ➤ Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1989 - 1992
- Publish Location: ➤ Washington, DC - Washington, D.C
“Long-term embrittlement of cast duplex stainless steels in LWR systems” Subjects and Themes:
- Subjects: Embrittlement - Light water reactors - Stainless Steel - Steel, Stainless
- Places: United States
Edition Identifiers:
- The Open Library ID: OL17598992M - OL18059997M - OL15375804M - OL15396164M - OL18071052M
- Online Computer Library Center (OCLC) ID: 31404269
Access and General Info:
- First Year Published: 1989
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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6Embrittlement of engineering alloys
By C. L. Briant
“Embrittlement of engineering alloys” Metadata:
- Title: ➤ Embrittlement of engineering alloys
- Author: C. L. Briant
- Language: English
- Number of Pages: Median: 623
- Publisher: ➤ Academic Pr - Elsevier Science & Technology Books - Academic Press
- Publish Date: 1983 - 2013
- Publish Location: New York
“Embrittlement of engineering alloys” Subjects and Themes:
- Subjects: Alloys - Embrittlement
Edition Identifiers:
- The Open Library ID: OL9281735M - OL7327087M - OL39531211M - OL3502447M
- Library of Congress Control Number (LCCN): 82022771
- All ISBNs: 148328865X - 0123418259 - 9781483288659 - 9780123418258
Access and General Info:
- First Year Published: 1983
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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7TR-EDB, test reactor embrittlement data base, version 1
By Friedemann Stallmann
“TR-EDB, test reactor embrittlement data base, version 1” Metadata:
- Title: ➤ TR-EDB, test reactor embrittlement data base, version 1
- Author: Friedemann Stallmann
- Language: English
- Number of Pages: Median: 107
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1994
- Publish Location: Washington, DC
“TR-EDB, test reactor embrittlement data base, version 1” Subjects and Themes:
- Subjects: Nuclear reactors - Databases - Materials - Testing - Embrittlement
Edition Identifiers:
- The Open Library ID: OL15396297M - OL18071119M - OL16388274M
Access and General Info:
- First Year Published: 1994
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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8Improved embrittlement correlations for reactor pressure vessel steels
By E. D. Eason
“Improved embrittlement correlations for reactor pressure vessel steels” Metadata:
- Title: ➤ Improved embrittlement correlations for reactor pressure vessel steels
- Author: E. D. Eason
- Language: English
- Number of Pages: Median: 115
- Publisher: ➤ United States Government Printing Office - Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1998
- Publish Location: Washington, DC
“Improved embrittlement correlations for reactor pressure vessel steels” Subjects and Themes:
- Subjects: ➤ Mathematical models - Steel - Materials - Embrittlement - Nuclear reactors - Effect of radiation on - Nuclear pressure vessels
Edition Identifiers:
- The Open Library ID: OL17701030M - OL50666807M - OL17603779M
- Online Computer Library Center (OCLC) ID: 43598725
- All ISBNs: 0160629705 - 9780160629709
Access and General Info:
- First Year Published: 1998
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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9Space shuttle main engine high pressure fuel turbopump turbine blade cracking
By Henry Lee
“Space shuttle main engine high pressure fuel turbopump turbine blade cracking” Metadata:
- Title: ➤ Space shuttle main engine high pressure fuel turbopump turbine blade cracking
- Author: Henry Lee
- Language: English
- Publisher: ➤ National Aeronautics and Space Administration, George C. Marshall Space Flight Center - For sale by National Technical Information Service
- Publish Date: 1988
- Publish Location: ➤ [Springfield, Va - [Marshall Space Flight Center, Ala.?]
“Space shuttle main engine high pressure fuel turbopump turbine blade cracking” Subjects and Themes:
- Subjects: Blades - Embrittlement - Hydrogen - Turbines
Edition Identifiers:
- The Open Library ID: OL14661932M - OL17658321M
Access and General Info:
- First Year Published: 1988
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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10Guidelines for prediction of irradiation embrittlement of operating WWER-440 reactor pressure vessels
By International Atomic Energy Agency
“Guidelines for prediction of irradiation embrittlement of operating WWER-440 reactor pressure vessels” Metadata:
- Title: ➤ Guidelines for prediction of irradiation embrittlement of operating WWER-440 reactor pressure vessels
- Author: ➤ International Atomic Energy Agency
- Language: English
- Number of Pages: Median: 69
- Publisher: ➤ International Atomic Energy Agency - Intl Atomic Energy Agency
- Publish Date: 2005
- Publish Location: Vienna
“Guidelines for prediction of irradiation embrittlement of operating WWER-440 reactor pressure vessels” Subjects and Themes:
- Subjects: Steel - Materials - Effect of radiation on - Nuclear pressure vessels - Embrittlement
Edition Identifiers:
- The Open Library ID: OL12857818M - OL18239684M
- All ISBNs: 9201056052 - 9789201056054
Access and General Info:
- First Year Published: 2005
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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11Atom probe tomography characterization of the solute distributions in a neutron-irradiated and annealed pressure vessel steel weld
By M. K. Miller
“Atom probe tomography characterization of the solute distributions in a neutron-irradiated and annealed pressure vessel steel weld” Metadata:
- Title: ➤ Atom probe tomography characterization of the solute distributions in a neutron-irradiated and annealed pressure vessel steel weld
- Author: M. K. Miller
- Language: English
- Number of Pages: Median: 13
- Publisher: ➤ United States Government Printing Office - U.S. Nuclear Regulatory Commission
- Publish Date: 2000
- Publish Location: Washington, DC
“Atom probe tomography characterization of the solute distributions in a neutron-irradiated and annealed pressure vessel steel weld” Subjects and Themes:
- Subjects: ➤ Steel - Materials - Embrittlement - Welded joints - Effect of radiation on - Nuclear pressure vessels - Atom-probe field ion microscopy
Edition Identifiers:
- The Open Library ID: OL50666073M - OL17603485M
- Online Computer Library Center (OCLC) ID: 48178383
- All ISBNs: 9780160614675 - 0160614678
Author's Alternative Names:
"Miller, Michael Kenneth", "Miller, M.K", "Miller, Michael, 1958-", "Miller, Michael K. 19..-.... ingénieur" and "Miller, M.K. (Michael Kenneth)"Access and General Info:
- First Year Published: 2000
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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12PR-EDB, power reactor embrittlement data base, version 1
By Friedemann Stallmann
“PR-EDB, power reactor embrittlement data base, version 1” Metadata:
- Title: ➤ PR-EDB, power reactor embrittlement data base, version 1
- Author: Friedemann Stallmann
- Language: English
- Publisher: ➤ Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1990
- Publish Location: Washington, DC
“PR-EDB, power reactor embrittlement data base, version 1” Subjects and Themes:
- Subjects: Computer programs - Steel - Defects - Nuclear pressure vessels - Embrittlement
Edition Identifiers:
- The Open Library ID: OL18053823M - OL15362220M
Access and General Info:
- First Year Published: 1990
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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13Comparison of irradiation-induced shifts of Kjc and charpy impact toughness for reactor pressure vessel steels
By M. A. Sokolov
“Comparison of irradiation-induced shifts of Kjc and charpy impact toughness for reactor pressure vessel steels” Metadata:
- Title: ➤ Comparison of irradiation-induced shifts of Kjc and charpy impact toughness for reactor pressure vessel steels
- Author: M. A. Sokolov
- Language: English
- Number of Pages: Median: 69
- Publisher: ➤ United States Government Printing Office - Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2000
- Publish Location: Washington, DC
“Comparison of irradiation-induced shifts of Kjc and charpy impact toughness for reactor pressure vessel steels” Subjects and Themes:
- Subjects: ➤ Steel - Materials - Effect of radiation on - Nuclear pressure vessels - Cracking - Embrittlement
Edition Identifiers:
- The Open Library ID: OL50667630M - OL16089980M
- All ISBNs: 0160614643 - 9780160614644
Access and General Info:
- First Year Published: 2000
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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14Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems
By O. K. Chopra
“Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems” Metadata:
- Title: ➤ Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems
- Author: O. K. Chopra
- Language: English
- Number of Pages: Median: 58
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1991 - 1994
- Publish Location: ➤ Washington, DC - Washington, D.C
“Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems” Subjects and Themes:
- Subjects: ➤ Effect of temperature on - Embrittlement - Light water reactors - Materials - R-curves - Stainless Steel - Steel, Stainless
Edition Identifiers:
- The Open Library ID: OL16998175M - OL15387098M
Access and General Info:
- First Year Published: 1991
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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15Radiation embrittlement of the neutron shield tank from the Shippingport reactor
By O. K. Chopra
“Radiation embrittlement of the neutron shield tank from the Shippingport reactor” Metadata:
- Title: ➤ Radiation embrittlement of the neutron shield tank from the Shippingport reactor
- Author: O. K. Chopra
- Language: English
- Number of Pages: Median: 38
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1991
- Publish Location: Washington, DC
“Radiation embrittlement of the neutron shield tank from the Shippingport reactor” Subjects and Themes:
- Subjects: Ferritic steel - Nuclear reactors - Effect of radiation on - Shielding (Radiation) - Embrittlement
Edition Identifiers:
- The Open Library ID: OL17678669M - OL14693493M
Access and General Info:
- First Year Published: 1991
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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16Radiation effects on reactor pressure vessel supports
By R. Johnson
“Radiation effects on reactor pressure vessel supports” Metadata:
- Title: ➤ Radiation effects on reactor pressure vessel supports
- Author: R. Johnson
- Language: English
- Publisher: ➤ Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1996
- Publish Location: Washington, DC
“Radiation effects on reactor pressure vessel supports” Subjects and Themes:
- Subjects: Steel - Testing - Effect of radiation on - Nuclear pressure vessels - Embrittlement
Edition Identifiers:
- The Open Library ID: OL13567619M - OL17698206M
- Online Computer Library Center (OCLC) ID: 39366700
Access and General Info:
- First Year Published: 1996
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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17Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants
By N. Soneda
“Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants” Metadata:
- Title: ➤ Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants
- Author: N. Soneda
- Language: English
- Number of Pages: Median: 432
- Publisher: Elsevier Science & Technology
- Publish Date: 2014
“Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants” Subjects and Themes:
- Subjects: ➤ Nuclear pressure vessels - Nuclear reactors - TECHNOLOGY & ENGINEERING - Mechanical - Effect of radiation on - Steel - Embrittlement
Edition Identifiers:
- The Open Library ID: OL37113350M - OL33449903M
- Online Computer Library Center (OCLC) ID: 890444932 - 891381822
- All ISBNs: 9781845699673 - 0857096478 - 9780857096470 - 184569967X
Access and General Info:
- First Year Published: 2014
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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18Neutron irradiation embrittlement of reactor pressure vessel steels
By L. E. Steele
“Neutron irradiation embrittlement of reactor pressure vessel steels” Metadata:
- Title: ➤ Neutron irradiation embrittlement of reactor pressure vessel steels
- Author: L. E. Steele
- Language: English
- Number of Pages: Median: 235
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 1975
- Publish Location: Vienna
“Neutron irradiation embrittlement of reactor pressure vessel steels” Subjects and Themes:
- Subjects: Effect of radiation on - Embrittlement - Nuclear pressure vessels - Steel - Nuclear engineering
Edition Identifiers:
- The Open Library ID: OL5253151M
- Online Computer Library Center (OCLC) ID: 1670459
- Library of Congress Control Number (LCCN): 75326034
- All ISBNs: 9201550758 - 9789201550750
Access and General Info:
- First Year Published: 1975
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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19The effect of Ob2s, Hb2sO, and Nb2s on the fatigue crack growth behavior of an gas + gbs titanium alloy at 24C and 177C
By Stephen W. Smith
“The effect of Ob2s, Hb2sO, and Nb2s on the fatigue crack growth behavior of an gas + gbs titanium alloy at 24C and 177C” Metadata:
- Title: ➤ The effect of Ob2s, Hb2sO, and Nb2s on the fatigue crack growth behavior of an gas + gbs titanium alloy at 24C and 177C
- Author: Stephen W. Smith
- Language: English
- Publisher: ➤ National Aeronautics and Space Administration, Langley Research Center - Available from NASA Center for AeroSpace Information (CASI)
- Publish Date: 2001
- Publish Location: Hanover MD - Hampton, Va
“The effect of Ob2s, Hb2sO, and Nb2s on the fatigue crack growth behavior of an gas + gbs titanium alloy at 24C and 177C” Subjects and Themes:
- Subjects: Crack propagation - Embrittlement - Fatigue (Materials) - Fatigue tests - Titanium alloys
Edition Identifiers:
- The Open Library ID: OL18479200M
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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20The effect of O₂, H₂O, and N₂ on the fatigue crack growth behavior of an Ü + Ý titanium alloy at 24C̊ and 177C̊
By Stephen W. Smith
“The effect of O₂, H₂O, and N₂ on the fatigue crack growth behavior of an Ü + Ý titanium alloy at 24C̊ and 177C̊” Metadata:
- Title: ➤ The effect of O₂, H₂O, and N₂ on the fatigue crack growth behavior of an Ü + Ý titanium alloy at 24C̊ and 177C̊
- Author: Stephen W. Smith
- Language: English
- Publisher: ➤ National Aeronautics and Space Administration, Langley Research Center - Available from NASA Center for AeroSpace Information (CASI)
- Publish Date: 2001
- Publish Location: Hanover MD - Hampton, Va
“The effect of O₂, H₂O, and N₂ on the fatigue crack growth behavior of an Ü + Ý titanium alloy at 24C̊ and 177C̊” Subjects and Themes:
- Subjects: Crack propagation - Embrittlement - Fatigue (Materials) - Fatigue tests - Titanium alloys
Edition Identifiers:
- The Open Library ID: OL16046871M
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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21Thermal aging effects in refractory metal alloys
By Joseph R. Stephens
“Thermal aging effects in refractory metal alloys” Metadata:
- Title: ➤ Thermal aging effects in refractory metal alloys
- Author: Joseph R. Stephens
- Language: English
- Publisher: ➤ National Aeronautics and Space Administration, Lewis Research Center
- Publish Date: 1986
- Publish Location: [Cleveland, Ohio
“Thermal aging effects in refractory metal alloys” Subjects and Themes:
- Subjects: ➤ Aging (Metallurgy) - Alloys - Auxiliary power supply - Embrittlement - Fatigue - Heat resistant alloys - High temperature - Hydrogen embrittlement - Microstructure - Niobium alloys - Refractory metal alloys - Space power reactors - Space vehicles - Tantalum alloys - Thermal degradation
Edition Identifiers:
- The Open Library ID: OL16151583M
Access and General Info:
- First Year Published: 1986
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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22Temper embrittlement of alloy steels
By Symposium on Temper Embrittlement of Alloy Steels Atlantic City 1971.
“Temper embrittlement of alloy steels” Metadata:
- Title: ➤ Temper embrittlement of alloy steels
- Author: ➤ Symposium on Temper Embrittlement of Alloy Steels Atlantic City 1971.
- Language: English
- Number of Pages: Median: 135
- Publisher: ➤ American Society for Testing and Materials
- Publish Date: 1972
- Publish Location: Philadelphia
“Temper embrittlement of alloy steels” Subjects and Themes:
- Subjects: Congresses - Embrittlement - Steel alloys - Tempering
Edition Identifiers:
- The Open Library ID: OL5478456M
- Online Computer Library Center (OCLC) ID: 419600
- Library of Congress Control Number (LCCN): 73185535
Access and General Info:
- First Year Published: 1972
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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23Liquid-metal embrittlement
By Alex Zurichenko
“Liquid-metal embrittlement” Metadata:
- Title: Liquid-metal embrittlement
- Author: Alex Zurichenko
- Language: English
- Number of Pages: Median: 20
- Publisher: ➤ Aerospace Technology Division, Library of Congress
- Publish Date: 1966
- Publish Location: [Washington]
“Liquid-metal embrittlement” Subjects and Themes:
- Subjects: Bibliography - Embrittlement - Liquid metals - Metals - Testing
Edition Identifiers:
- The Open Library ID: OL5560933M
- Library of Congress Control Number (LCCN): 67060596
Access and General Info:
- First Year Published: 1966
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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24WWER pressure vessel steel embrittlement
By S. Chatterjee
“WWER pressure vessel steel embrittlement” Metadata:
- Title: ➤ WWER pressure vessel steel embrittlement
- Author: S. Chatterjee
- Language: English
- Number of Pages: Median: 63
- Publisher: Bhabha Atomic Reseearch Centre
- Publish Date: 2002
- Publish Location: Mumbai
“WWER pressure vessel steel embrittlement” Subjects and Themes:
- Subjects: Embrittlement - Pressure vessels - Steel
Edition Identifiers:
- The Open Library ID: OL3717413M
- Library of Congress Control Number (LCCN): 2003328619
Access and General Info:
- First Year Published: 2002
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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25Vydelenie vtoroĭ fazy v tverdykh rastvorakh
By Ustinovshchikov, I͡U. I.
“Vydelenie vtoroĭ fazy v tverdykh rastvorakh” Metadata:
- Title: ➤ Vydelenie vtoroĭ fazy v tverdykh rastvorakh
- Author: Ustinovshchikov, I͡U. I.
- Language: rus
- Number of Pages: Median: 171
- Publisher: "Nauka"
- Publish Date: 1988
- Publish Location: Moskva
“Vydelenie vtoroĭ fazy v tverdykh rastvorakh” Subjects and Themes:
- Subjects: Solid Solutions - Analysis - Alloys - Embrittlement - Solid state physics
Edition Identifiers:
- The Open Library ID: OL2246665M
- Online Computer Library Center (OCLC) ID: 21624366
- Library of Congress Control Number (LCCN): 89121315
- All ISBNs: 9785020058804 - 5020058807
Access and General Info:
- First Year Published: 1988
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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26Embrittlement by the localized crack environment
By R. P. Gangloff
“Embrittlement by the localized crack environment” Metadata:
- Title: ➤ Embrittlement by the localized crack environment
- Author: R. P. Gangloff
- Language: English
- Number of Pages: Median: 491
- Publisher: Metallurgical Society of AIME
- Publish Date: 1984
- Publish Location: Warrendale, Pa
“Embrittlement by the localized crack environment” Subjects and Themes:
- Subjects: Metals - Congresses - Stress corrosion - Cracking - Embrittlement
Edition Identifiers:
- The Open Library ID: OL2872522M
- Online Computer Library Center (OCLC) ID: 11671944
- Library of Congress Control Number (LCCN): 84061499
- All ISBNs: 0895204800 - 9780895204806
Access and General Info:
- First Year Published: 1984
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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27Irradiation embrittlement and creep in fuel cladding and core components
By British Nuclear Energy Society
“Irradiation embrittlement and creep in fuel cladding and core components” Metadata:
- Title: ➤ Irradiation embrittlement and creep in fuel cladding and core components
- Author: British Nuclear Energy Society
- Language: English
- Number of Pages: Median: 310
- Publisher: British Nuclear Energy Society
- Publish Date: 1973
- Publish Location: London
“Irradiation embrittlement and creep in fuel cladding and core components” Subjects and Themes:
- Subjects: ➤ Materials - Congresses - Creep - Embrittlement - Nuclear reactors - Effect of radiation on - Metals - Nuclear reactors, materials - Metals, effect of radiation on - Metals, creep
Edition Identifiers:
- The Open Library ID: OL5092175M
- Library of Congress Control Number (LCCN): 74163733
- All ISBNs: 9780901948748 - 0901948748
Access and General Info:
- First Year Published: 1973
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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28Embrittlement by liquid and solid metals
By M. H. Kamdar
“Embrittlement by liquid and solid metals” Metadata:
- Title: ➤ Embrittlement by liquid and solid metals
- Author: M. H. Kamdar
- Language: English
- Number of Pages: Median: 589
- Publisher: The Society
- Publish Date: 1984
- Publish Location: Warrendale, Pa
“Embrittlement by liquid and solid metals” Subjects and Themes:
- Subjects: Congresses - Metals - Embrittlement
Edition Identifiers:
- The Open Library ID: OL3191264M
- Library of Congress Control Number (LCCN): 83062937
Access and General Info:
- First Year Published: 1984
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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29Radiation embrittlement and surveillance of nuclear reactor pressure vessels
By L. E. Steele
“Radiation embrittlement and surveillance of nuclear reactor pressure vessels” Metadata:
- Title: ➤ Radiation embrittlement and surveillance of nuclear reactor pressure vessels
- Author: L. E. Steele
- Language: English
- Number of Pages: Median: 220
- Publisher: ➤ Americal Society for Testing and Materials
- Publish Date: 1983
- Publish Location: Philadelphia, Pa
“Radiation embrittlement and surveillance of nuclear reactor pressure vessels” Subjects and Themes:
- Subjects: Steel - Congresses - Effect of radiation on - Nuclear pressure vessels - Embrittlement
Edition Identifiers:
- The Open Library ID: OL17907143M
- Online Computer Library Center (OCLC) ID: 10267982
- Library of Congress Control Number (LCCN): 83070258
Access and General Info:
- First Year Published: 1983
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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30Characterization study of temper embrittlement of chromium-molybdenum steels
By American Petroleum Institute. Division of Refining
“Characterization study of temper embrittlement of chromium-molybdenum steels” Metadata:
- Title: ➤ Characterization study of temper embrittlement of chromium-molybdenum steels
- Author: ➤ American Petroleum Institute. Division of Refining
- Language: English
- Number of Pages: Median: 126
- Publisher: American Petroleum Institute
- Publish Date: 1982
- Publish Location: ➤ Washington, D.C. (2101 L St., N.W., Washington 20037)
“Characterization study of temper embrittlement of chromium-molybdenum steels” Subjects and Themes:
- Subjects: Chromium-molybdenum steel - Brittleness - Embrittlement
Edition Identifiers:
- The Open Library ID: OL3068817M
- Library of Congress Control Number (LCCN): 82166540
Access and General Info:
- First Year Published: 1982
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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31Radiation embrittlement of nuclear reactor pressure vessel steels
By L. E. Steele
“Radiation embrittlement of nuclear reactor pressure vessel steels” Metadata:
- Title: ➤ Radiation embrittlement of nuclear reactor pressure vessel steels
- Author: L. E. Steele
- Language: English
- Number of Pages: Median: 408
- Publisher: ASTM
- Publish Date: 1993
- Publish Location: Philadelphia, PA
“Radiation embrittlement of nuclear reactor pressure vessel steels” Subjects and Themes:
- Subjects: Steel - Congresses - Effect of radiation on - Nuclear pressure vessels - Embrittlement
Edition Identifiers:
- The Open Library ID: OL1501106M
- Online Computer Library Center (OCLC) ID: 28153500
- Library of Congress Control Number (LCCN): 93179079
- All ISBNs: 0803114788 - 9780803114784
Access and General Info:
- First Year Published: 1993
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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32Radiation embrittlement of nuclear reactor pressure vessel steels
By L. E. Steele
“Radiation embrittlement of nuclear reactor pressure vessel steels” Metadata:
- Title: ➤ Radiation embrittlement of nuclear reactor pressure vessel steels
- Author: L. E. Steele
- Language: English
- Number of Pages: Median: 277
- Publisher: ASTM
- Publish Date: 1989
- Publish Location: Philadelphia, PA
“Radiation embrittlement of nuclear reactor pressure vessel steels” Subjects and Themes:
- Subjects: Steel - Congresses - Effect of radiation on - Nuclear pressure vessels - Embrittlement
Edition Identifiers:
- The Open Library ID: OL17641438M
- Online Computer Library Center (OCLC) ID: 20220053
- Library of Congress Control Number (LCCN): 88037454 - 89139588
- All ISBNs: 0803111878 - 9780803111875
Access and General Info:
- First Year Published: 1989
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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33Results of Charpy V-notch impact testing of structural steel specimens irradiated at 3̃0 ̊C to 1 x 10¹⁶ neutrons/cm² in a commercial reactors cavity
By S. K. Iskander
“Results of Charpy V-notch impact testing of structural steel specimens irradiated at 3̃0 ̊C to 1 x 10¹⁶ neutrons/cm² in a commercial reactors cavity” Metadata:
- Title: ➤ Results of Charpy V-notch impact testing of structural steel specimens irradiated at 3̃0 ̊C to 1 x 10¹⁶ neutrons/cm² in a commercial reactors cavity
- Author: S. K. Iskander
- Language: English
- Publisher: ➤ Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1997
- Publish Location: Washington, D.C
“Results of Charpy V-notch impact testing of structural steel specimens irradiated at 3̃0 ̊C to 1 x 10¹⁶ neutrons/cm² in a commercial reactors cavity” Subjects and Themes:
- Subjects: ➤ Notched bar testing - Materials - Structural Steel - Flux (Metallurgy) - Nuclear reactors - Embrittlement - Testing
Edition Identifiers:
- The Open Library ID: OL17596105M
- Online Computer Library Center (OCLC) ID: 42241582
Access and General Info:
- First Year Published: 1997
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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34Radiation effects on reactor pressure vessel supports
By R. E. Johnson
“Radiation effects on reactor pressure vessel supports” Metadata:
- Title: ➤ Radiation effects on reactor pressure vessel supports
- Author: R. E. Johnson
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission
- Publish Date: 1996
- Publish Location: Washington, DC
“Radiation effects on reactor pressure vessel supports” Subjects and Themes:
- Subjects: Steel - Effect of radiation on - Nuclear pressure vessels - Embrittlement
Edition Identifiers:
- The Open Library ID: OL17805937M
- Online Computer Library Center (OCLC) ID: 34955668
Access and General Info:
- First Year Published: 1996
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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35High temperature embrittleness of Cu-Cr alloy
By Hisashi Suzuki
“High temperature embrittleness of Cu-Cr alloy” Metadata:
- Title: ➤ High temperature embrittleness of Cu-Cr alloy
- Author: Hisashi Suzuki
- Language: English
- Number of Pages: Median: 15
- Publisher: ➤ National Technical Information Service, distributor - National Aeronautics and Space Administration
- Publish Date: 1988
- Publish Location: ➤ Washington, D.C - [Springfield, Va.?
“High temperature embrittleness of Cu-Cr alloy” Subjects and Themes:
- Subjects: Chromium-copper alloys - Effect of temperature on - Embrittlement
Edition Identifiers:
- The Open Library ID: OL22211237M
Access and General Info:
- First Year Published: 1988
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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36High temperture embrittleness of Cu-Cr alloy
By Hisashi Suzuki
“High temperture embrittleness of Cu-Cr alloy” Metadata:
- Title: ➤ High temperture embrittleness of Cu-Cr alloy
- Author: Hisashi Suzuki
- Language: English
- Number of Pages: Median: 15
- Publisher: ➤ National Technical Information Service, distributor - National Aeronautics and Space Administration
- Publish Date: 1988
- Publish Location: ➤ Washington, D.C - [Springfield, Va.?
“High temperture embrittleness of Cu-Cr alloy” Subjects and Themes:
- Subjects: ➤ Chromium-copper alloys - Embrittlement - Effect of temperature on - Temperature effects - Microstructure - Chromium alloys - Copper alloys
Edition Identifiers:
- The Open Library ID: OL17683671M
Access and General Info:
- First Year Published: 1988
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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37A comparison of the relative importance of copper precipitates and point defect clusters in reactor pressure vessel embrittlement
By R. E. Stoller
“A comparison of the relative importance of copper precipitates and point defect clusters in reactor pressure vessel embrittlement” Metadata:
- Title: ➤ A comparison of the relative importance of copper precipitates and point defect clusters in reactor pressure vessel embrittlement
- Author: R. E. Stoller
- Language: English
- Number of Pages: Median: 36
- Publisher: ➤ U.S. Nuclear Regulatory Commission
- Publish Date: 1994
- Publish Location: Washington, DC
“A comparison of the relative importance of copper precipitates and point defect clusters in reactor pressure vessel embrittlement” Subjects and Themes:
- Subjects: Steel - Effect of radiation on - Nuclear pressure vessels - Embrittlement
Edition Identifiers:
- The Open Library ID: OL17451029M
- Online Computer Library Center (OCLC) ID: 37113418
Access and General Info:
- First Year Published: 1994
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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38In-situ TEM observations of gallium penetration into aluminum grain boundaries
By Richard Charles Hugo
“In-situ TEM observations of gallium penetration into aluminum grain boundaries” Metadata:
- Title: ➤ In-situ TEM observations of gallium penetration into aluminum grain boundaries
- Author: Richard Charles Hugo
- Language: English
- Number of Pages: Median: 84
- Publish Date: 1993
“In-situ TEM observations of gallium penetration into aluminum grain boundaries” Subjects and Themes:
- Subjects: ➤ Aluminum - Transmission electron microscopes - Embrittlement - Grain boundaries - Gallium - Penetration resistance
Edition Identifiers:
- The Open Library ID: OL16960912M
Access and General Info:
- First Year Published: 1993
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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39A study of liquid metal embrittlement of aluminum by mercury and gallium via crack growth analysis and atomistic modeling
By Yi Liu
“A study of liquid metal embrittlement of aluminum by mercury and gallium via crack growth analysis and atomistic modeling” Metadata:
- Title: ➤ A study of liquid metal embrittlement of aluminum by mercury and gallium via crack growth analysis and atomistic modeling
- Author: Yi Liu
- Language: English
- Number of Pages: Median: 147
- Publish Date: 1992
“A study of liquid metal embrittlement of aluminum by mercury and gallium via crack growth analysis and atomistic modeling” Subjects and Themes:
- Subjects: Aluminum alloys - Aluminum - Fracture - Embrittlement
Edition Identifiers:
- The Open Library ID: OL16949271M
Access and General Info:
- First Year Published: 1992
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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40Mechanical properties of thermally aged cast stainless steels from Shippingport Reactor components
By O. K. Chopra
“Mechanical properties of thermally aged cast stainless steels from Shippingport Reactor components” Metadata:
- Title: ➤ Mechanical properties of thermally aged cast stainless steels from Shippingport Reactor components
- Author: O. K. Chopra
- Language: English
- Number of Pages: Median: 154
- Publisher: ➤ Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1995
- Publish Location: Washington, D.C
“Mechanical properties of thermally aged cast stainless steels from Shippingport Reactor components” Subjects and Themes:
- Subjects: ➤ Embrittlement - Equipment and supplies - Fracture - Maintainability - Nuclear reactors - Stainless Steel - Steel, Stainless
Edition Identifiers:
- The Open Library ID: OL17595777M
- Online Computer Library Center (OCLC) ID: 43649109
Access and General Info:
- First Year Published: 1995
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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41Heat-affected zone embrittlement on weldable Al-Zn-Mg alloys
By Richard L. Williams
“Heat-affected zone embrittlement on weldable Al-Zn-Mg alloys” Metadata:
- Title: ➤ Heat-affected zone embrittlement on weldable Al-Zn-Mg alloys
- Author: Richard L. Williams
- Language: English
- Number of Pages: Median: 62
- Publish Date: 1983
“Heat-affected zone embrittlement on weldable Al-Zn-Mg alloys” Subjects and Themes:
- Subjects: Aluminum alloys - Alloys - Welding - Embrittlement
Edition Identifiers:
- The Open Library ID: OL16562566M
Access and General Info:
- First Year Published: 1983
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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42Embrittlement data base, version 1
By J. A. Wang
“Embrittlement data base, version 1” Metadata:
- Title: ➤ Embrittlement data base, version 1
- Author: J. A. Wang
- Language: English
- Publisher: ➤ Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1997
- Publish Location: Washington, DC
“Embrittlement data base, version 1” Subjects and Themes:
- Subjects: Materials - Embrittlement - Nuclear pressure vessels - Databases
Edition Identifiers:
- The Open Library ID: OL15483643M
Access and General Info:
- First Year Published: 1997
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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43The Effect of aging at 343⁰C on the microstructure and mechanical properties of type 308 stainless steel weldments
By D. J. Alexander
“The Effect of aging at 343⁰C on the microstructure and mechanical properties of type 308 stainless steel weldments” Metadata:
- Title: ➤ The Effect of aging at 343⁰C on the microstructure and mechanical properties of type 308 stainless steel weldments
- Author: D. J. Alexander
- Language: English
- Number of Pages: Median: 44
- Publisher: ➤ [Supt. of Docs., U.S. G.P.O., distributor - U.S. Nuclear Regulatory Commission
- Publish Date: 2000
- Publish Location: Washington, DC
“The Effect of aging at 343⁰C on the microstructure and mechanical properties of type 308 stainless steel weldments” Subjects and Themes:
- Subjects: ➤ Embrittlement - Stainless Steel - Materials - Nuclear power plants - Effect of temperature on - Deterioration - Light water reactors - Piping
Edition Identifiers:
- The Open Library ID: OL17598940M
- Online Computer Library Center (OCLC) ID: 46592947
Access and General Info:
- First Year Published: 2000
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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44Reactor pressure vessel status report
“Reactor pressure vessel status report” Metadata:
- Title: ➤ Reactor pressure vessel status report
- Language: English
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
- Publish Date: 1996
- Publish Location: Washington, DC
“Reactor pressure vessel status report” Subjects and Themes:
- Subjects: ➤ Steel - Reliability - Materials - Embrittlement - Effect of radiation on - Nuclear power plants - Nuclear pressure vessels
Edition Identifiers:
- The Open Library ID: OL14491365M
- Online Computer Library Center (OCLC) ID: 38540866
Access and General Info:
- First Year Published: 1996
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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Downloads Are Not Available:
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45Models for embrittlement recovery due to annealing of reactor pressure vessel steels
By E. D. Eason
“Models for embrittlement recovery due to annealing of reactor pressure vessel steels” Metadata:
- Title: ➤ Models for embrittlement recovery due to annealing of reactor pressure vessel steels
- Author: E. D. Eason
- Language: English
- Number of Pages: Median: 69
- Publisher: ➤ U.S. Nuclear Regulatory Commission
- Publish Date: 1995
- Publish Location: Washington, DC
“Models for embrittlement recovery due to annealing of reactor pressure vessel steels” Subjects and Themes:
- Subjects: Steel - Mathematical models - Effect of radiation on - Nuclear pressure vessels - Embrittlement
Edition Identifiers:
- The Open Library ID: OL17453467M
- Online Computer Library Center (OCLC) ID: 34660264
Access and General Info:
- First Year Published: 1995
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.
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46Yielding and fracture of Fe-30 [gamma] Cr alloys subjected to 475⁰ C-embrittlement
By Rune Lagneborg
“Yielding and fracture of Fe-30 [gamma] Cr alloys subjected to 475⁰ C-embrittlement” Metadata:
- Title: ➤ Yielding and fracture of Fe-30 [gamma] Cr alloys subjected to 475⁰ C-embrittlement
- Author: Rune Lagneborg
- Language: English
- Number of Pages: Median: 40
- Publisher: ➤ exp. (Ingeniörsvetenskapsakedemien)
- Publish Date: 1967
- Publish Location: Stockholm
“Yielding and fracture of Fe-30 [gamma] Cr alloys subjected to 475⁰ C-embrittlement” Subjects and Themes:
- Subjects: Chromium-iron alloys - Embrittlement - Testing
Edition Identifiers:
- The Open Library ID: OL5381048M
- Library of Congress Control Number (LCCN): 72417108
Access and General Info:
- First Year Published: 1967
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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47Temper-embrittlement studies
By R. F. Knight
“Temper-embrittlement studies” Metadata:
- Title: Temper-embrittlement studies
- Author: R. F. Knight
- Language: English
- Number of Pages: Median: 67
- Publisher: ➤ Dept. of Energy, Mines and Resources, Mines Branch
- Publish Date: 1968
- Publish Location: Ottawa
“Temper-embrittlement studies” Subjects and Themes:
- Subjects: Embrittlement - Iron-molybdenum alloys - Steel - Tempering
Edition Identifiers:
- The Open Library ID: OL4797710M
- Library of Congress Control Number (LCCN): 75518808
Access and General Info:
- First Year Published: 1968
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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