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Designing Radiation Resistance in Materials for Fusion Energy

Annual review of materials research, 2014-07, Vol.44 (1), p.241-267

2014

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Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations

Scripta materialia, 2018-01, Vol.143 (C), p.154-160

2018

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Effect of H and He irradiation on cavity formation and blistering in ceramics

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2012-09, Vol.286, p.4-19

Zinkle, S.J.

2012

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Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

Acta materialia, 2016-07, Vol.113 (C), p.230-244

2016

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Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

Journal of nuclear materials, 2014-05, Vol.448 (1-3), p.420-435

2014

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Introduction to the special issue on the technical status of materials for a fusion reactor

Nuclear fusion, 2017-06, Vol.57 (9), p.92001

2017

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On the use of SRIM for calculating vacancy production: Quick calculation and full-cascade options

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2021-09, Vol.503 (C), p.11-29

2021

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Towards a greater understanding of serrated flows in an Al-containing high-entropy-based alloy

International journal of plasticity, 2019-04, Vol.115, p.71-92

2019

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Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications

Nuclear fusion, 2017-06, Vol.57 (9), p.92005

2017

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Multimodal options for materials research to advance the basis for fusion energy in the ITER era

Nuclear fusion, 2013-10, Vol.53 (10), p.104024

2013

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Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

Journal of nuclear materials, 2014-12, Vol.455 (1-3), p.277-291

2014

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Evaluation of high strength, high conductivity CuNiBe alloys for fusion energy applications

Journal of nuclear materials, 2014-06, Vol.449 (1-3), p.277-289

Zinkle, S.J.

2014

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Phase instabilities in austenitic steels during particle bombardment at high and low dose rates

Materials & design, 2022-05, Vol.217 (na), p.110588, Article 110588

2022

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Investigation of the thermal and neutron irradiation response of BAM-11 bulk metallic glass

Journal of nuclear materials, 2019-12, Vol.526 (C), p.151771, Article 151771

2019

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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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Specification of CuCrZr alloy properties after various thermo-mechanical treatments and design allowables including neutron irradiation effects

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.904-907

2011

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Status of R&D activities on materials for fusion power reactors

Nuclear fusion, 2007-10, Vol.47 (10), p.S696-S717

2007

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On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materials

Journal of nuclear materials, 2000-12, Vol.283-287, p.349-352

2000

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Operating temperature windows for fusion reactor structural materials

Fusion engineering and design, 2000-11, Vol.51, p.55-71

2000

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Overview of materials research for fusion reactors

Fusion Engineering and Design, 2002-11, Vol.61, p.13-25

2002

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Thermal conductivity degradation of ceramic materials due to low temperature, low dose neutron irradiation

Journal of nuclear materials, 2005-04, Vol.340 (2-3), p.187-202

2005

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Fusion materials science and technology research opportunities now and during the ITER era

Fusion engineering and design, 2014-10, Vol.89 (7-8), p.1579-1585

2014

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Materials to deliver the promise of fusion power – progress and challenges

Journal of nuclear materials, 2004-08, Vol.329, p.12-19

2004

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Kinetics of coarsening of helium bubbles during implantation and post-implantation annealing

Journal of nuclear materials, 2007-04, Vol.361 (2-3), p.149-159

2007

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Quantifying defect production in solids at finite temperatures: Thermally-activated correlated defect recombination corrections to DPA (CRC-DPA)

Journal of nuclear materials, 2023-04, Vol.577, p.154292, Article 154292

2023

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Designing Radiation Resistance in Materials for Fusion Energy

Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations

Effect of H and He irradiation on cavity formation and blistering in ceramics

Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

Introduction to the special issue on the technical status of materials for a fusion reactor

On the use of SRIM for calculating vacancy production: Quick calculation and full-cascade options

Towards a greater understanding of serrated flows in an Al-containing high-entropy-based alloy

Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications

Multimodal options for materials research to advance the basis for fusion energy in the ITER era

Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

Evaluation of high strength, high conductivity CuNiBe alloys for fusion energy applications

Phase instabilities in austenitic steels during particle bombardment at high and low dose rates

Investigation of the thermal and neutron irradiation response of BAM-11 bulk metallic glass

Microstructure of neutron-irradiated iron before and after tensile deformation

Specification of CuCrZr alloy properties after various thermo-mechanical treatments and design allowables including neutron irradiation effects

Status of R&D activities on materials for fusion power reactors

On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materials

Operating temperature windows for fusion reactor structural materials

Overview of materials research for fusion reactors

Thermal conductivity degradation of ceramic materials due to low temperature, low dose neutron irradiation

Fusion materials science and technology research opportunities now and during the ITER era

Materials to deliver the promise of fusion power – progress and challenges

Kinetics of coarsening of helium bubbles during implantation and post-implantation annealing

Quantifying defect production in solids at finite temperatures: Thermally-activated correlated defect recombination corrections to DPA (CRC-DPA)

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