Carmen Garcia-Rosales

Carmen Garcia-Rosales

Universidad de Navarra

H-index: 37

Europe-Spain

About Carmen Garcia-Rosales

Carmen Garcia-Rosales, With an exceptional h-index of 37 and a recent h-index of 22 (since 2020), a distinguished researcher at Universidad de Navarra, specializes in the field of Nuclear fusion, materials for fusion application, plasma-wall interaction, material science, tungsten alloys.

His recent articles reflect a diverse array of research interests and contributions to the field:

Radiation-induced effects in self-passivating W-Cr-Y alloy

Mock-ups fabrication by HRP technology with advanced W-alloy monoblocks for DEMO divertor target

Hydrodynamics and electrical insulation of PbLi flow with SiC flow channel inserts in a strong magnetic field

Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method and helium presence

Deuterium retention in displacement-damaged selfpassivating tungsten alloys

Development of irradiation tolerant tungsten alloys for high temperature nuclear applications

Fabrication and characterization of SiC sandwich material for Flow Channel Inserts in HT-DCLL blanket by gel casting

Oxidation-resistant tungsten-based alloys as plasma-facing materials in nuclear fusion reactors

Carmen Garcia-Rosales Information

University

Position

CEIT and Tecnun ()

Citations(all)

5437

Citations(since 2020)

1784

Cited By

4184

hIndex(all)

37

hIndex(since 2020)

22

i10Index(all)

86

i10Index(since 2020)

40

Email

University Profile Page

Universidad de Navarra

Google Scholar

View Google Scholar Profile

Carmen Garcia-Rosales Skills & Research Interests

Nuclear fusion

materials for fusion application

plasma-wall interaction

material science

tungsten alloys

Top articles of Carmen Garcia-Rosales

Title

Journal

Author(s)

Publication Date

Radiation-induced effects in self-passivating W-Cr-Y alloy

Journal of Nuclear Materials

OV Ogorodnikova

A Nikitin

S Rogozkin

E Sal

C García-Rosales

...

2024/4/3

Mock-ups fabrication by HRP technology with advanced W-alloy monoblocks for DEMO divertor target

Fusion Engineering and Design

Francesco Crea

Bernd Böswirth

Emanuele Cacciotti

Andrei Galatanu

Henri Greuner

...

2024/4/1

Hydrodynamics and electrical insulation of PbLi flow with SiC flow channel inserts in a strong magnetic field

Fusion Engineering and Design

A Brēķis

I Krastiņš

B Pérez Polo

J Echeberria

K Kravalis

...

2023/9/1

Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method and helium presence

Journal of Nuclear Materials

Z Harutyunyan

OV Ogorodnikova

Yu Gasparyan

A Umerenkova

Y Wang

...

2023/5/1

Deuterium retention in displacement-damaged selfpassivating tungsten alloys

H Maier

T Schwarz-Selinger

E Sal

C Garcia-Rosales

K Hunger

...

2022

Development of irradiation tolerant tungsten alloys for high temperature nuclear applications

Nuclear Fusion

Dmitry Terentyev

Petra Jenus

Elisa Sal

Aleksandr Zinovev

Chih-Cheng Chang

...

2022/6/27

Fabrication and characterization of SiC sandwich material for Flow Channel Inserts in HT-DCLL blanket by gel casting

Nuclear Materials and Energy

Beatriz Perez

Asier Bergara

Artūrs Brēķis

Marta Malo

Javier Garcia-Goikoetxea

...

2022/3/1

Oxidation-resistant tungsten-based alloys as plasma-facing materials in nuclear fusion reactors

C Garcia-Rosales

E Sal

K Hunger

K Schlüter

M Gago

...

2022

Joining of self-passivating W-Cr-Y alloy to ferritic-martensitic steel by hot isostatic pressing

Fusion Engineering and Design

E Sal

J de Prado

M Sánchez

A Ureña

C García-Rosales

2021/9/1

Microstructural and mechanical characterization of self-passivating W-Eurofer joints processed by brazing technique

Journal of Composites Science

Essam B Moustafa

Mazen Sharaf

Ghazi Alsoruji

Ahmed O Mosleh

SS Mohamed

...

2023/10/30

Deuterium Retention in Self-Passivating Tungsten Alloy: Effect of Displacement Damage

H Maier

T Schwarz-Selinger

E Sal

C Garcia-Rosales

K Hunger

...

2021

High heat flux performance of self-passivating W-10Cr-0.5 Y alloy for the blanket first wall of DEMO

C Garcia-Rosales

E Sal

H Greuner

S Elgeti

2021

On the electrical properties under irradiation of porous SiC prepared by sacrificial template technique

Fusion Engineering and Design

Marta Malo

Carlota Soto

Carmen García-Rosales

Teresa Hernández

2020/3/1

Mitigation of MHD phenomena in DCLL blankets by Flow Channel Inserts based on a SiC-sandwich material concept

Fusion Engineering and Design

C Soto

S Smolentsev

C García-Rosales

2020/2/1

Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys

Nuclear Materials and Energy

Elisa Sal

Carmen García-Rosales

Karsten Schlueter

Katja Hunger

Mauricio Gago

...

2020/8/1

See List of Professors in Carmen Garcia-Rosales University(Universidad de Navarra)