Neutron Irradiation Effects on the Corrosion of Zircaloy-4 in a Pressurized Water Reactor Environment

Zirconium in the Nuclear Industry: 18th International Symposium ◽

10.1520/stp159720160085 ◽

2018 ◽

pp. 448-490 ◽

Cited By ~ 2

Author(s):

Bruce F. Kammenzind ◽

Jason A. Gruber ◽

Ram Bajaj ◽

James D. Smee

Keyword(s):

Neutron Irradiation ◽

Pressurized Water Reactor ◽

Irradiation Effects ◽

Pressurized Water ◽

Water Reactor

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Effect of neutron irradiation embrittlement on cyclic hardening behavior of core shroud assembly in pressurized water reactor under beyond-design basis earthquake

10.1063/1.5140306 ◽

2019 ◽

Cited By ~ 1

Author(s):

Jong-Sung Kim ◽

Jun-Min Seo ◽

Yun-Jae Kim ◽

Young-In Choi ◽

Chang-Sik Oh ◽

...

Keyword(s):

Neutron Irradiation ◽

Cyclic Hardening ◽

Pressurized Water Reactor ◽

Irradiation Embrittlement ◽

Pressurized Water ◽

Water Reactor ◽

Hardening Behavior ◽

Design Basis ◽

Core Shroud

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Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes: Part II. Morphology of hydrides investigated at different magnifications and their interaction with the processes of plastic deformation

Metallurgical and Materials Transactions A ◽

10.1007/s11661-003-0092-2 ◽

2003 ◽

Vol 34 (3) ◽

pp. 567-578 ◽

Cited By ~ 41

Author(s):

Miléna Veleva ◽

Sylvie Arsene ◽

Marie-Christine Record ◽

Jean Luc Bechade ◽

Jinbo Bai

Keyword(s):

Mechanical Properties ◽

Plastic Deformation ◽

Boiling Water ◽

Boiling Water Reactor ◽

Pressurized Water Reactor ◽

Irradiation Effects ◽

Pressurized Water ◽

Water Reactor ◽

Hydride Embrittlement

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The ASYNT Adjoint Synthesis Method for Neutron Irradiation Assessment of VVER/Pressurized Water Reactor Pressure Vessel

Nuclear Science and Engineering ◽

10.13182/nse97-a24477 ◽

1997 ◽

Vol 126 (2) ◽

pp. 239-244 ◽

Cited By ~ 1

Author(s):

Sergey I. Belousov ◽

Krassimira D. Ilieva

Keyword(s):

Neutron Irradiation ◽

Pressure Vessel ◽

Synthesis Method ◽

Reactor Pressure Vessel ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

Reactor Pressure

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Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes: Part I. Hydride embrittlement in stress-relieved, annealed, and recrystallized ZIRCALOYs at 20 °C and 300 °C

Metallurgical and Materials Transactions A ◽

10.1007/s11661-003-0091-3 ◽

2003 ◽

Vol 34 (3) ◽

pp. 553-566 ◽

Cited By ~ 36

Author(s):

S. Arsene ◽

J. B. Bai ◽

P. Bompard

Keyword(s):

Mechanical Properties ◽

Boiling Water ◽

Boiling Water Reactor ◽

Pressurized Water Reactor ◽

Irradiation Effects ◽

Pressurized Water ◽

Water Reactor ◽

Hydride Embrittlement

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Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes: Part III. Mechanical behavior of hydride in stress-relieved annealed and recrystallized ZIRCALOYs at 20 °C and 300 °C

Metallurgical and Materials Transactions A ◽

10.1007/s11661-003-0093-1 ◽

2003 ◽

Vol 34 (3) ◽

pp. 579-588 ◽

Cited By ~ 37

Author(s):

Sylvie Arsene ◽

Jinbo Bai ◽

Philipe Bompard

Keyword(s):

Mechanical Properties ◽

Mechanical Behavior ◽

Boiling Water ◽

Boiling Water Reactor ◽

Pressurized Water Reactor ◽

Irradiation Effects ◽

Pressurized Water ◽

Water Reactor ◽

Hydride Embrittlement

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10 MWe Pressurized Water Reactor for Defense Terrestrial Power Application

22nd Intersociety Energy Conversion Engineering Conference ◽

10.2514/6.1987-9337 ◽

1987 ◽

Author(s):

W. H. Arnold ◽

M. C. Gross ◽

W. S. Shingler ◽

R. M. Vijuk

Keyword(s):

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

Power Application

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Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor

Kerntechnik ◽

10.3139/124.110077 ◽

2010 ◽

Vol 75 (1-2) ◽

pp. 12-19 ◽

Cited By ~ 4

Author(s):

P. Tusheva ◽

F. Schäfer ◽

N. Reinke ◽

E. Altstadt ◽

U. Rohde ◽

...

Keyword(s):

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

Management Measures ◽

Accident Management ◽

Station Blackout

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Analyses of loads on reactor pressure vessel internals in a pressurized water reactor due to a loss-of-coolant accident considering fluid-structure interaction

Kerntechnik ◽

10.3139/124.110123 ◽

2010 ◽

Vol 75 (6) ◽

pp. 311-315

Author(s):

P. Akimov ◽

L. Obereisenbuchner

Keyword(s):

Pressure Vessel ◽

Fluid Structure Interaction ◽

Reactor Pressure Vessel ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

Structure Interaction ◽

Loss Of Coolant Accident ◽

Loss Of Coolant ◽

Reactor Pressure

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Nuclear reactor instrumentation. Pressurized water reactor (PWR) of VVER design. Monitoring adequate cooling within the core during cold shutdown

10.3403/02178475 ◽

2001 ◽

Keyword(s):

Nuclear Reactor ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

The Core

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Light Water Reactor Sustainability Program: Analysis of Pressurized Water Reactor Station Blackout Caused by External Flooding Using the RISMC Toolkit

10.2172/1168617 ◽

2014 ◽

Cited By ~ 1

Author(s):

Curtis Smith ◽

Diego Mandelli ◽

Steven Prescott ◽

Andrea Alfonsi ◽

Cristian Rabiti ◽

...

Keyword(s):

Program Analysis ◽

Light Water Reactor ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Light Water ◽

Water Reactor ◽

Station Blackout ◽

Sustainability Program

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