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The Creative Economy: Arts, Cultural Value and Society in Practice

1, 2024

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Planning for a City of Culture: Creative Urbanism in Toronto and New York

Goldberg-Miller, Shoshanah B. D.

1st edition., 2017

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Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel

Nuclear materials and energy, 2023-09, Vol.36, p.101469, Article 101469

2023

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Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils

Nuclear materials and energy, 2023-06, Vol.35, p.101436, Article 101436

2023

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Sensitization and Stress Corrosion Crack Response of Dual Certified Type 304/304L Stainless Steel

Corrosion (Houston, Tex.), 2018-07, Vol.74 (7), p.737-746

2018

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Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7wt%Mo dispersion fuels

Journal of nuclear materials, 2015-03, Vol.458 (C), p.115-121

2015

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Microstructure of the irradiated U3Si2/Al silicide dispersion fuel

Journal of nuclear materials, 2011-12, Vol.419 (1-3), p.97-104

2011

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The complex structural and chemical nature of monolithic U-10Mo fuel and Zr barrier layer

Journal of nuclear materials, 2023-01, Vol.573, p.154083, Article 154083

2023

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Understanding the effect of crack tip deformation on fatigue crack growth behavior in 300-series austenitic stainless steel

International journal of fatigue, 2019-08, Vol.125, p.261-270

2019

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Dynamic Secondary Ion Mass Spectrometry (SIMS) Imaging of Materials for the Nuclear Industry: Historical Perspectives and Recent Advances

Microscopy and microanalysis, 2017-07, Vol.23 (S1), p.2208-2209

2017

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The role of surface deformation in the oxidation response of type 304 SS in high temperature deaerated water

Corrosion science, 2018-08, Vol.141, p.88-96

2018

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Effect of heat treatment on the microstructure of medium burn-up U-Mo monolithic fuel foils

Journal of nuclear materials, 2024-05, Vol.593 (15), p.155002, Article 155002

2024

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Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements

Journal of nuclear materials, 2021-12, Vol.557 (C), p.153280, Article 153280

2021

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Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG)

Journal of nuclear materials, 2020-04, Vol.531 (C), p.151964, Article 151964

2020

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Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density

Journal of nuclear materials, 2017-08, Vol.492 (C), p.195-203

2017

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Engagement in the city: How arts and culture impact development in urban areas Engagement in the city: How arts and culture impact development in urban areas , edited by Bryna Bobick & Leigh Hersey Lexington Books Publication date: 03/12/2021 Pages: 244 Lexington Books, 3/12/21, 244 pp., Publisher Location: Lanham, MD, US$100.00: edited by Bryna Bobick & Leigh Hersey Lexington Books Publication date: 03/12/2021 Pages: 244 Lexington Books, 3/12/21, 244 pp., Publisher Location: Lanham, MD, US$100.00

Local development & society, 2022-01, Vol.3 (1), p.125-127

B.D. Goldberg-Miller, Shoshanah

2022

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Large-scale application of membrane contactors for gas transfer from or to ultrapure water

Separation and purification technology, 1998-08, Vol.14 (1), p.189-200

1998

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3D reconstructions of irradiated UMo fuel to understand breaching effects in ZrN diffusion barriers

Journal of nuclear materials, 2018-11, Vol.510, p.431-436

2018

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Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7 wt%Mo dispersion fuels

Journal of nuclear materials, 2015-03, Vol.458 (C), p.115-121

2015

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STEM-EDS/EELS and APT characterization of ZrN coatings on UMo fuel kernels

Journal of nuclear materials, 2018-12, Vol.511, p.174-182

2018

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HT9 swelling in high burnup fast reactor fuel pin components

Journal of nuclear materials, 2019-06, Vol.519, p.205-216

2019

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Creative city strategies on the municipal agenda in New York

City, culture and society, 2019-06, Vol.17, p.26-37

Goldberg-Miller, Shoshanah B.D.

2019

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Analysis of irradiated U-7wt%Mo dispersion fuel microstructures using automated image processing

Journal of nuclear materials, 2016-07, Vol.475 (C), p.94-104

2016

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Transmission electron microscopy investigation of neutron irradiated Si and ZrN coated UMo particles prepared using FIB

Journal of nuclear materials, 2018-01, Vol.498, p.60-70

2018

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Thermal stability of fission gas bubble superlattice in irradiated U–10Mo fuel

Journal of nuclear materials, 2015-09, Vol.464 (C), p.1-5

2015

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The Creative Economy: Arts, Cultural Value and Society in Practice

Planning for a City of Culture: Creative Urbanism in Toronto and New York

Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel

Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils

Sensitization and Stress Corrosion Crack Response of Dual Certified Type 304/304L Stainless Steel

Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7wt%Mo dispersion fuels

Microstructure of the irradiated U3Si2/Al silicide dispersion fuel

The complex structural and chemical nature of monolithic U-10Mo fuel and Zr barrier layer

Understanding the effect of crack tip deformation on fatigue crack growth behavior in 300-series austenitic stainless steel

Dynamic Secondary Ion Mass Spectrometry (SIMS) Imaging of Materials for the Nuclear Industry: Historical Perspectives and Recent Advances

The role of surface deformation in the oxidation response of type 304 SS in high temperature deaerated water

Effect of heat treatment on the microstructure of medium burn-up U-Mo monolithic fuel foils

Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements

Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG)

Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density

Large-scale application of membrane contactors for gas transfer from or to ultrapure water

3D reconstructions of irradiated UMo fuel to understand breaching effects in ZrN diffusion barriers

Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7 wt%Mo dispersion fuels

STEM-EDS/EELS and APT characterization of ZrN coatings on UMo fuel kernels

HT9 swelling in high burnup fast reactor fuel pin components

Creative city strategies on the municipal agenda in New York

Analysis of irradiated U-7wt%Mo dispersion fuel microstructures using automated image processing

Transmission electron microscopy investigation of neutron irradiated Si and ZrN coated UMo particles prepared using FIB

Thermal stability of fission gas bubble superlattice in irradiated U–10Mo fuel

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