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Helium accumulation in metals during irradiation – where do we stand?

Journal of nuclear materials, 2003-12, Vol.323 (2), p.229-242

2003

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Correlation between microstructure and mechanical properties in the age-hardenable Cu-Cr-Zr alloy

Journal of nuclear materials, 2021-04, Vol.546, p.152775, Article 152775

2021

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Investigation of hydrogen diffusivity in Zr-2.5%Nb alloy pressure tube material using Metallography and Neutron Radiography

Journal of nuclear materials, 2021-02, Vol.544, p.152679, Article 152679

2021

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Stress-reorientation of hydrides and hydride embrittlement of Zr–2.5 wt% Nb pressure tube alloy

Journal of nuclear materials, 2004-02, Vol.325 (1), p.26-33

2004

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Microstructure of neutron-irradiated iron before and after tensile deformation

Journal of nuclear materials, 2006-06, Vol.351 (1), p.269-284

2006

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Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging

Journal of nuclear materials, 2023-07, Vol.580, p.154414, Article 154414

2023

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Effects of hydrogen on thermal creep behaviour of Zircaloy fuel cladding

Journal of nuclear materials, 2018-01, Vol.498, p.20-32

2018

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Effect of radial hydride on delayed hydride cracking behaviour of Zr-2.5Nb pressure tube material

Journal of nuclear materials, 2020-12, Vol.542, p.152457, Article 152457

2020

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Isothermal stress reorientation of hydrides in Zr-2.5Nb pressure tube alloy

Journal of nuclear materials, 2022-02, Vol.559, p.153440, Article 153440

2022

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Microstructure and fracture toughness of 850°C quenched and aged Zr-2.5Nb alloy

Journal of nuclear materials, 2024-08, Vol.597, p.155133, Article 155133

2024

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Delayed hydride cracking of Zr-2.5%Nb pressure tube material due to partially constrained precipitates

Journal of nuclear materials, 2019-01, Vol.513, p.129-142

2019

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Study of grain growth kinetics of Zr-2.5%Nb alloy quenched from (α+β) and β-phase region

Journal of nuclear materials, 2024-05, Vol.593, p.154979, Article 154979

2024

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Effect of annealing treatment on the creep behaviour of Zr-2.5Nb alloy

Journal of nuclear materials, 2024-04, Vol.592, p.154949, Article 154949

2024

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Effect of radial hydride on room temperature fracture toughness of Zr-2.5Nb pressure tube material

Journal of nuclear materials, 2021-02, Vol.544, p.152681, Article 152681

2021

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Effect of radial hydride fraction on fracture toughness of CWSR Zr-2.5%Nb pressure tube material between ambient and 300 °C temperatures

Journal of nuclear materials, 2018-09, Vol.508, p.546-555

2018

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The microstructure and associated tensile properties of irradiated fcc and bcc metals

Journal of nuclear materials, 2000, Vol.276 (1), p.114-122

2000

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Stability and mobility of defect clusters and dislocation loops in metals

Journal of nuclear materials, 2000, Vol.276 (1), p.65-77

2000

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Effect of manufacturing route on thermal creep behaviour of Zr-2.5Nb pressure tube alloy used in Indian PHWR

Journal of nuclear materials, 2022-10, Vol.569, p.153903, Article 153903

2022

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Influence of hydrogen content on fracture toughness of CWSR Zr–2.5Nb pressure tube alloy

Journal of nuclear materials, 2013-01, Vol.432 (1-3), p.87-93

2013

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Effect of radial hydrides on fracture behavior of Zr-2.5Nb pressure tube material

Journal of nuclear materials, 2024-01, Vol.588, p.154800, Article 154800

2024

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Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy

Journal of nuclear materials, 2005-06, Vol.342 (1), p.164-178

2005

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Effect of deuterium content on fracture toughness of Zr-2.5Nb pressure tube material in the temperature range of ambient to 300 °C

Journal of nuclear materials, 2017-12, Vol.496, p.182-192

2017

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Influence of hydride orientation on fracture toughness of CWSR Zr-2.5%Nb pressure tube material between RT and 300 °C

Journal of nuclear materials, 2017-05, Vol.488, p.231-244

2017

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Stress assisted oxide cracking of Zr-2.5Nb pressure tube material

Journal of nuclear materials, 2020-08, Vol.536, p.152187, Article 152187

2020

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3D-AP and positron annihilation study of precipitation behavior in Cu–Cr–Zr alloy

Journal of nuclear materials, 2009-04, Vol.386, p.852-855

2009

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Helium accumulation in metals during irradiation – where do we stand?

Correlation between microstructure and mechanical properties in the age-hardenable Cu-Cr-Zr alloy

Investigation of hydrogen diffusivity in Zr-2.5%Nb alloy pressure tube material using Metallography and Neutron Radiography

Stress-reorientation of hydrides and hydride embrittlement of Zr–2.5 wt% Nb pressure tube alloy

Microstructure of neutron-irradiated iron before and after tensile deformation

Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging

Effects of hydrogen on thermal creep behaviour of Zircaloy fuel cladding

Effect of radial hydride on delayed hydride cracking behaviour of Zr-2.5Nb pressure tube material

Isothermal stress reorientation of hydrides in Zr-2.5Nb pressure tube alloy

Microstructure and fracture toughness of 850°C quenched and aged Zr-2.5Nb alloy

Delayed hydride cracking of Zr-2.5%Nb pressure tube material due to partially constrained precipitates

Study of grain growth kinetics of Zr-2.5%Nb alloy quenched from (α+β) and β-phase region

Effect of annealing treatment on the creep behaviour of Zr-2.5Nb alloy

Effect of radial hydride on room temperature fracture toughness of Zr-2.5Nb pressure tube material

Effect of radial hydride fraction on fracture toughness of CWSR Zr-2.5%Nb pressure tube material between ambient and 300 °C temperatures

The microstructure and associated tensile properties of irradiated fcc and bcc metals

Stability and mobility of defect clusters and dislocation loops in metals

Effect of manufacturing route on thermal creep behaviour of Zr-2.5Nb pressure tube alloy used in Indian PHWR

Influence of hydrogen content on fracture toughness of CWSR Zr–2.5Nb pressure tube alloy

Effect of radial hydrides on fracture behavior of Zr-2.5Nb pressure tube material

Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy

Effect of deuterium content on fracture toughness of Zr-2.5Nb pressure tube material in the temperature range of ambient to 300 °C

Influence of hydride orientation on fracture toughness of CWSR Zr-2.5%Nb pressure tube material between RT and 300 °C

Stress assisted oxide cracking of Zr-2.5Nb pressure tube material

3D-AP and positron annihilation study of precipitation behavior in Cu–Cr–Zr alloy

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