15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Latest Publications

TOTAL DOCUMENTS

253

(FIVE YEARS 0)

H-INDEX

(FIVE YEARS 0)

Published By John Wiley & Sons, Inc.

9781118456835, 9781118132418

Latest Documents Most Cited Documents Contributed Authors Related Sources Related Keywords

Effect of Thermal Aging on SCC, Material Properties and Fracture Toughness of Stainless Steel Weld Metals

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118456835.ch91 ◽

2012 ◽

pp. 883-900 ◽

Cited By ~ 1

Author(s):

T. Lucas ◽

R. G. Ballinger ◽

H. Hanninen ◽

T. Saukkonen

Keyword(s):

Fracture Toughness ◽

Stainless Steel ◽

Thermal Aging ◽

Material Properties ◽

Steel Weld ◽

Weld Metals ◽

Stainless Steel Weld

Download Full-text

The Effect of Temperature on the Crack Growth Rate of Stainless Steel and NI-Alloys in Simulated BWR Environment

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118456835.ch87 ◽

2012 ◽

pp. 827-838 ◽

Cited By ~ 1

Author(s):

Johan Stjärnsäter ◽

Anders Jenssen ◽

Christer Jansson ◽

Karen Gott ◽

Björn Forssgren ◽

...

Keyword(s):

Growth Rate ◽

Stainless Steel ◽

Crack Growth Rate ◽

Crack Growth ◽

Effect Of Temperature ◽

Ni Alloys

Download Full-text

Role of Cavity Formation on Crack Growth of Cold-Worked Carbon Steel, TT 690 and MA 600 in High Temperature Water

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118456835.ch8 ◽

2012 ◽

pp. 55-69

Author(s):

Koji Arioka ◽

Tomoki Miyamoto ◽

Takuyo Yamada ◽

Takumi Terachi

Keyword(s):

High Temperature ◽

Carbon Steel ◽

Crack Growth ◽

Cavity Formation ◽

High Temperature Water ◽

Cold Worked ◽

Temperature Water

Download Full-text

Microstructure and SCC of Alloy X-750

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118456835.ch76 ◽

2012 ◽

pp. 719-740

Author(s):

Peter L. Andresen ◽

Juan Flores-Preciado ◽

Martin M. Morra ◽

Robert Carter

Download Full-text

Questions & Answers

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118456835.ch71 ◽

2012 ◽

pp. 681-681

Download Full-text

Electrochemical Study of Pre - and Post-Transition Corrosion of Zr Alloys in PWR Coolant

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118456835.ch68 ◽

2012 ◽

pp. 655-663

Author(s):

Jan Macák ◽

Radek Novotný ◽

Petr Sajdl ◽

Veronika Renčiuková ◽

Věra Vrtílková

Keyword(s):

Electrochemical Study ◽

Zr Alloys

Download Full-text

Questions & Answers

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118456835.ch64 ◽

2012 ◽

pp. 627-631

Download Full-text

PWR Fuel Deposit Analysis at a B&W Plant with a 24 Month Fuel Cycle

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118456835.ch63 ◽

2012 ◽

pp. 621-625

Author(s):

Mike G. Pop ◽

Larry S. Lamanna ◽

Richard Harne ◽

John Riddle

Keyword(s):

Fuel Cycle

Download Full-text

NRC Research Activities on Environmentally-Assisted Fatigue

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118456835.ch61 ◽

2012 ◽

pp. 605-616

Author(s):

Gary L. Stevens ◽

Robert L. Tregoning

Keyword(s):

Research Activities

Download Full-text

Questions & Answers

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118456835.ch56 ◽

2012 ◽

pp. 545-545

Download Full-text

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water ReactorsLatest Publications

TOTAL DOCUMENTS

H-INDEX

Published By John Wiley & Sons, Inc.

Effect of Thermal Aging on SCC, Material Properties and Fracture Toughness of Stainless Steel Weld Metals

The Effect of Temperature on the Crack Growth Rate of Stainless Steel and NI-Alloys in Simulated BWR Environment

Role of Cavity Formation on Crack Growth of Cold-Worked Carbon Steel, TT 690 and MA 600 in High Temperature Water

Microstructure and SCC of Alloy X-750

Questions & Answers

Electrochemical Study of Pre - and Post-Transition Corrosion of Zr Alloys in PWR Coolant

Questions & Answers

PWR Fuel Deposit Analysis at a B&W Plant with a 24 Month Fuel Cycle

NRC Research Activities on Environmentally-Assisted Fatigue

Questions & Answers

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Latest Publications