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Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants

Soneda, Naoki

1, 2014

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Depth distribution of Frank loop defects formed in ion-irradiated stainless steel and its dependence on Si addition

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2015-12, Vol.365, p.503-508

2015

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Atom Probe Tomography Interlaboratory Study on Clustering Analysis in Experimental Data Using the Maximum Separation Distance Approach

Microscopy and microanalysis, 2019-04, Vol.25 (2), p.356-366

2019

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Structural integrity of reactor pressure vessels (3): Mechanism and prediction of neutron irradiation embrittlement

Journal of the Atomic Energy Society of Japan, 2023, Vol.65 (3), p.179-182

Soneda, Naoki

2023

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Structural integrity of reactor pressure vessels (2): Overview of the framework to guarantee the structural integrity

Journal of the Atomic Energy Society of Japan, 2022, Vol.64 (11), p.632-636

Soneda, Naoki

2022

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Structural integrity of reactor pressure vessels (1): Overview of the framework to guarantee the structural integrity

Journal of the Atomic Energy Society of Japan, 2022, Vol.64 (10), p.581-585

Soneda, Naoki

2022

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Effects of irradiation induced Cu clustering on Vickers hardness and electrical resistivity of Fe–Cu model alloys

Journal of nuclear materials, 2014-09, Vol.452 (1-3), p.241-247

2014

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Effects of solute elements on hardening and microstructural evolution in neutron-irradiated and thermally-aged reactor pressure vessel model alloys

Journal of nuclear science and technology, 2016-10, Vol.53 (10), p.1546-1553

2016

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Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels

Journal of engineering for gas turbines and power, 2010-10, Vol.132 (10)

2010

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Radiation Defects Formed in Ion-Irradiated 316L Stainless Steel Model Alloys with Different Si Additions

Materials transactions, 2015, Vol.56 (9), p.1549-1552

2015

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Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan

Journal of engineering for gas turbines and power, 2010-10, Vol.132 (10)

2010

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Interaction Analysis between Edge Dislocation and Self Interstitial Type Dislocation Loop in BCC Iron Using Molecular Dynamics

Materials transactions, 2005-03, Vol.46 (3), p.463-468

2005

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Microstructural Characterization of RPV Materials Irradiated to High Fluences at High Flux

Journal of ASTM International, 2009-07, Vol.6 (7), p.1-16

2009

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First-principles calculations of vacancy–solute element interactions in body-centered cubic iron

Acta materialia, 2009-12, Vol.57 (20), p.5947-5955

2009

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Ab Initio Electronic Structure Study of α-Zirconium and Hydrogen

Materials transactions, 2008-12, Vol.49 (12), p.2765-2769

2008

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Study of the effect of Ni on solute clustering in α-Fe

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2019-08, Vol.453, p.28-31

2019

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Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens

Journal of pressure vessel technology, 2012-04, Vol.134 (2)

2012

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Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Materials

Journal of ASTM International, 2010-03, Vol.7 (3), p.1-20

2010

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Evaluation of Fracture Toughness by Master Curve Approach Using Miniature Specimens

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A, 2011, Vol.77 (777), p.680-684

2011

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First-principles investigation on the composition of Ni-Si precipitates formed in irradiated stainless steels

Journal of nuclear materials, 2017-10, Vol.494, p.354-360

2017

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Hardening induced by energetic electron beam for Cu-Ti alloys

Japanese Journal of Applied Physics, 2014-05, Vol.53 (5S1), p.5-1-05FC04-5

2014

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Rational Determination of Lower-Bound Fracture Toughness Curves Using Master Curve Approach

Journal of pressure vessel technology, 2013-12, Vol.135 (6)

2013

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Fracture Toughness Evaluation of Japanese Reactor pressure Vessel Steels Using Master Curve Approach(Maintenance Inspection and Monitoring,<Special Issue>Power and Energy System Symposium)

Transactions of the Japan Society of Mechanical Engineers Series B, 2009/03/25, Vol.75(751), pp.436-438

2009

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On the Use of Density-Based Algorithms for the Analysis of Solute Clustering in Atom Probe Tomography Data

Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, p.2097-2113

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A Round Robin Experiment: Analysis of Solute Clustering from Atom Probe Tomography Data

Microscopy and microanalysis, 2016-07, Vol.22 (S3), p.666-667

2016

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Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants

Depth distribution of Frank loop defects formed in ion-irradiated stainless steel and its dependence on Si addition

Atom Probe Tomography Interlaboratory Study on Clustering Analysis in Experimental Data Using the Maximum Separation Distance Approach

Structural integrity of reactor pressure vessels (3): Mechanism and prediction of neutron irradiation embrittlement

Structural integrity of reactor pressure vessels (2): Overview of the framework to guarantee the structural integrity

Structural integrity of reactor pressure vessels (1): Overview of the framework to guarantee the structural integrity

Effects of irradiation induced Cu clustering on Vickers hardness and electrical resistivity of Fe–Cu model alloys

Effects of solute elements on hardening and microstructural evolution in neutron-irradiated and thermally-aged reactor pressure vessel model alloys

Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels

Radiation Defects Formed in Ion-Irradiated 316L Stainless Steel Model Alloys with Different Si Additions

Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan

Interaction Analysis between Edge Dislocation and Self Interstitial Type Dislocation Loop in BCC Iron Using Molecular Dynamics

Microstructural Characterization of RPV Materials Irradiated to High Fluences at High Flux

First-principles calculations of vacancy–solute element interactions in body-centered cubic iron

Ab Initio Electronic Structure Study of α-Zirconium and Hydrogen

Study of the effect of Ni on solute clustering in α-Fe

Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens

Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Materials

Evaluation of Fracture Toughness by Master Curve Approach Using Miniature Specimens

First-principles investigation on the composition of Ni-Si precipitates formed in irradiated stainless steels

Hardening induced by energetic electron beam for Cu-Ti alloys

Rational Determination of Lower-Bound Fracture Toughness Curves Using Master Curve Approach

Fracture Toughness Evaluation of Japanese Reactor pressure Vessel Steels Using Master Curve Approach(Maintenance Inspection and Monitoring,<Special Issue>Power and Energy System Symposium)

On the Use of Density-Based Algorithms for the Analysis of Solute Clustering in Atom Probe Tomography Data

A Round Robin Experiment: Analysis of Solute Clustering from Atom Probe Tomography Data

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