Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Latest Publications

TOTAL DOCUMENTS

130

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H-INDEX

(FIVE YEARS 0)

Published By John Wiley & Sons, Inc.

9781118787618, 9780873394758

Latest Documents Most Cited Documents Contributed Authors Related Sources Related Keywords

Effects of Neutron Irradiation on Positron Lifetime and Micro-Vickers Hardness of Fe-Cu Model Alloys and Reactor Pressure Vessel Steel

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118787618.ch88 ◽

2013 ◽

pp. 835-844 ◽

Cited By ~ 1

Author(s):

A. Hempel ◽

M. Hasegawa ◽

G. Brauer ◽

F. Plazaola ◽

M. Saneyasu ◽

...

Keyword(s):

Neutron Irradiation ◽

Vickers Hardness ◽

Pressure Vessel ◽

Positron Lifetime ◽

Reactor Pressure Vessel ◽

Pressure Vessel Steel ◽

Vessel Steel ◽

Reactor Pressure Vessel Steel ◽

Reactor Pressure

Intergranular Cracking of an Irradiated Ti-Stabilized Austenitic Stainless Steel Spacer Grid Sleeve from a VVER-440 Reactor

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118787618.ch99 ◽

2013 ◽

pp. 941-950

Author(s):

Ulla Ehrnstén ◽

Pertti Nenonen ◽

Pertti Aaltonen ◽

Risto Teräsvirta ◽

Ossi Hietanen

Keyword(s):

Stainless Steel ◽

Austenitic Stainless Steel ◽

Intergranular Cracking ◽

Spacer Grid

Stress Corrosion Cracking Tests of RPV Steels Under Simultaneous BWR Coolant and Irradiation Conditions

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118787618.ch92 ◽

2013 ◽

pp. 875-883

Author(s):

M. Ruščák ◽

J. Kysela ◽

A. Brožová ◽

O. Erben ◽

M. Postler ◽

...

Keyword(s):

Stress Corrosion ◽

Stress Corrosion Cracking ◽

Corrosion Cracking

Irradiation Behavior of Electricite De France PWR Vessel Steel

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118787618.ch85 ◽

2013 ◽

pp. 813-820 ◽

Cited By ~ 1

Author(s):

Christian Pichon ◽

Yves Grandjean ◽

Sébastien Saillet ◽

Georges Bezdikian ◽

Jean-Michel Frund

Keyword(s):

Vessel Steel ◽

Irradiation Behavior

Surface Modification for PWSCC Prevention of Alloy 600 by a Laser Cladding Technique

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118787618.ch82 ◽

2013 ◽

pp. 783-791

Author(s):

Shigeki Kasahara ◽

Masatoshi Sato ◽

Toshizo Ohya ◽

Masaya Kanikawa ◽

Hiroshi Kanasaki

Keyword(s):

Surface Modification ◽

Laser Cladding ◽

Alloy 600

Internal Oxidation and Embrittlement of Alloy 600

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118787618.ch8 ◽

2013 ◽

pp. 79-93 ◽

Cited By ~ 8

Author(s):

R.C. Newman ◽

T.S. Gendron ◽

P.M. Scott

Keyword(s):

Internal Oxidation ◽

Alloy 600

Status of Review of Applications and Issues of License Renewal by the Materials and Chemical Engineering Staff at the U.S. Nuclear Regulatory Commission

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118787618.ch78 ◽

2013 ◽

pp. 747-754

Author(s):

Merrilee Banic

Keyword(s):

Chemical Engineering ◽

Nuclear Regulatory Commission ◽

Regulatory Commission ◽

License Renewal ◽

Engineering Staff ◽

The U.S

EPRI R&D for Safe and Economic Long-Term Nuclear Plant Operation

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118787618.ch74 ◽

2013 ◽

pp. 712-724

Author(s):

Robin L. Jones ◽

John Carey ◽

Chris Wood

Keyword(s):

Nuclear Plant ◽

Plant Operation

Lead Assisted Stress Corrosion Cracking of Alloy 690

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118787618.ch73 ◽

2013 ◽

pp. 703-710 ◽

Cited By ~ 1

Author(s):

M.J. Psaila-Dombrowski ◽

F.H. Hua ◽

P.E. Doherty

Keyword(s):

Stress Corrosion ◽

Stress Corrosion Cracking ◽

Corrosion Cracking ◽

Alloy 690

Corrosion Control and Lay-up of the Crystal River-3 Steam Generators and Secondary Plant during an Extended Outage

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ◽

10.1002/9781118787618.ch67 ◽

2013 ◽

pp. 649-656

Author(s):

Rocky H. Thompson ◽

W. R. Bill Kassen

Keyword(s):

Corrosion Control ◽

Steam Generators ◽

Crystal River ◽

Secondary Plant

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water ReactorsLatest Publications

TOTAL DOCUMENTS

H-INDEX

Published By John Wiley & Sons, Inc.

Effects of Neutron Irradiation on Positron Lifetime and Micro-Vickers Hardness of Fe-Cu Model Alloys and Reactor Pressure Vessel Steel

Intergranular Cracking of an Irradiated Ti-Stabilized Austenitic Stainless Steel Spacer Grid Sleeve from a VVER-440 Reactor

Stress Corrosion Cracking Tests of RPV Steels Under Simultaneous BWR Coolant and Irradiation Conditions

Irradiation Behavior of Electricite De France PWR Vessel Steel

Surface Modification for PWSCC Prevention of Alloy 600 by a Laser Cladding Technique

Internal Oxidation and Embrittlement of Alloy 600

Status of Review of Applications and Issues of License Renewal by the Materials and Chemical Engineering Staff at the U.S. Nuclear Regulatory Commission

EPRI R&D for Safe and Economic Long-Term Nuclear Plant Operation

Lead Assisted Stress Corrosion Cracking of Alloy 690

Corrosion Control and Lay-up of the Crystal River-3 Steam Generators and Secondary Plant during an Extended Outage

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Latest Publications