Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle

Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49014s ◽

2010 ◽

pp. 252-252-24

Author(s):

Timothy J. Lampman ◽

Adrian Popescu ◽

Jose Freire-Canosa

Keyword(s):

Finite Element ◽

Finite Element Model ◽

Mechanical Load ◽

Element Model ◽

Fuel Bundle

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Study of Microstructure and Property Changes in Irradiated SS316 Wrapper of Fast Breeder Test Reactor

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49010s ◽

2010 ◽

pp. 196-196-14

Author(s):

C. N. Venkiteswaran ◽

V. Karthik ◽

P. Parameswaran ◽

N. G. Muralidharan ◽

V. Anandaraj ◽

...

Keyword(s):

Fast Breeder Test Reactor ◽

Test Reactor ◽

Property Changes

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Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49008s ◽

2010 ◽

pp. 164-164-12

Author(s):

J. H. Lee ◽

R. Kasada ◽

H. S. Cho ◽

A. Kimura

Keyword(s):

Ferritic Steels

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Subject Index

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49016s ◽

2010 ◽

pp. 279-279-2

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Interrelationship between True Stress—True Strain Behavior and Deformation Microstructure in the Plastic Deformation of Neutron-Irradiated or Work-Hardened Austenitic Stainless Steel

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49012s ◽

2010 ◽

pp. 220-220-18

Author(s):

K. Kondo ◽

Y. Miwa ◽

T. Tsukada ◽

S. Yamashita ◽

K. Nishinoiri

Keyword(s):

Plastic Deformation ◽

Stainless Steel ◽

Austenitic Stainless Steel ◽

True Strain ◽

True Stress ◽

Deformation Microstructure ◽

Strain Behavior

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Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49007s ◽

2010 ◽

pp. 153-153-11

Author(s):

Yutaka Nishiyama ◽

Masatake Yamaguchi ◽

Kunio Onizawa ◽

Akihiko Iwase ◽

Hiroshi Matsuzawa

Keyword(s):

Transition Temperature ◽

Grain Boundary ◽

Pressure Vessel ◽

Solute Segregation ◽

Reactor Pressure Vessel ◽

Brittle Transition ◽

Pressure Vessel Steels ◽

Brittle Transition Temperature ◽

Ductile To Brittle Transition ◽

Reactor Pressure

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Unusual Enhancement of Ductility Observed during Evolution of a “Deformation Wave” in 12Cr18Ni10Ti Stainless Steel Irradiated in BN-350

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49011s ◽

2010 ◽

pp. 210-210-10

Author(s):

M. N. Gusev ◽

O. P. Maksimkin ◽

I. S. Osipov ◽

N. S. Silniagina ◽

F. A. Garner

Keyword(s):

Stainless Steel ◽

Deformation Wave

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Kinetic Monte Carlo Simulation of Helium-Bubble Evolution in ODS Steels

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49009s ◽

2010 ◽

pp. 176-176-20

Author(s):

Akiyuki Takahashi ◽

Shahram Sharafat ◽

Koji Nagasawa ◽

Nasr Ghoniem

Keyword(s):

Monte Carlo Simulation ◽

Monte Carlo ◽

Kinetic Monte Carlo ◽

Helium Bubble ◽

Kinetic Monte Carlo Simulation ◽

Ods Steels ◽

Bubble Evolution

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Author Index

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49015s ◽

2010 ◽

pp. 277-277-2

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Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49005s ◽

2010 ◽

pp. 115-115-14

Author(s):

Hans -Werner Viehrig ◽

Jan Schuhknecht ◽

Udo Rindelhardt ◽

Frank -Peter Weiss

Keyword(s):

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Welding Seam ◽

Reactor Pressure

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Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle
Latest Publications

TOTAL DOCUMENTS

H-INDEX

Published By ASTM International

Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments

Study of Microstructure and Property Changes in Irradiated SS316 Wrapper of Fast Breeder Test Reactor

Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels

Subject Index

Interrelationship between True Stress—True Strain Behavior and Deformation Microstructure in the Plastic Deformation of Neutron-Irradiated or Work-Hardened Austenitic Stainless Steel

Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels

Unusual Enhancement of Ductility Observed during Evolution of a “Deformation Wave” in 12Cr18Ni10Ti Stainless Steel Irradiated in BN-350

Kinetic Monte Carlo Simulation of Helium-Bubble Evolution in ODS Steels

Author Index

Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Export Citation Format

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel CycleLatest Publications

TOTAL DOCUMENTS

H-INDEX

Published By ASTM International

Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments

Study of Microstructure and Property Changes in Irradiated SS316 Wrapper of Fast Breeder Test Reactor

Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels

Subject Index

Interrelationship between True Stress—True Strain Behavior and Deformation Microstructure in the Plastic Deformation of Neutron-Irradiated or Work-Hardened Austenitic Stainless Steel

Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels

Unusual Enhancement of Ductility Observed during Evolution of a “Deformation Wave” in 12Cr18Ni10Ti Stainless Steel Irradiated in BN-350

Kinetic Monte Carlo Simulation of Helium-Bubble Evolution in ODS Steels

Author Index

Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle
Latest Publications