Investigation of corrosion an high temperature oxidation of promising ATF cladding materials in the framework of the IL TROVATORE project

Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

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Investigation of corrosion an high temperature oxidation of promising ATF cladding materials in the framework of the IL TROVATORE project. / Grosse, Mirco M.; Van Loo, Koba; Frankberg, Erkka L.; Chonchong, Tang; Lambrinou, Konstantza; Di Fonzo, Fabio; Steinbrueck, Martin.

International Nuclear Fuel Cycle Conference and TOP FUEL 2019: Light Water Reactor Fuel Performance conference. ANS - American Nuclear Society, 2019. p. 274-279.

Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

Harvard

Grosse, MM, Van Loo, K, Frankberg, EL, Chonchong, T, Lambrinou, K, Di Fonzo, F & Steinbrueck, M 2019, Investigation of corrosion an high temperature oxidation of promising ATF cladding materials in the framework of the IL TROVATORE project. in International Nuclear Fuel Cycle Conference and TOP FUEL 2019: Light Water Reactor Fuel Performance conference. ANS - American Nuclear Society, pp. 274-279, 2019 - Global/Top Fuel, Seattle, Washington, United States, 2019-09-22. <https://www.researchgate.net/publication/337424404_Investigation_of_Corrosion_and_High_Temperature_Oxidation_of_Promising_ATF_Cladding_Materials_in_the_Framework_of_the_Il_Trovatore_Project>

APA

Grosse, M. M., Van Loo, K., Frankberg, E. L., Chonchong, T., Lambrinou, K., Di Fonzo, F., & Steinbrueck, M. (2019). Investigation of corrosion an high temperature oxidation of promising ATF cladding materials in the framework of the IL TROVATORE project. In International Nuclear Fuel Cycle Conference and TOP FUEL 2019: Light Water Reactor Fuel Performance conference (pp. 274-279). ANS - American Nuclear Society. https://www.researchgate.net/publication/337424404_Investigation_of_Corrosion_and_High_Temperature_Oxidation_of_Promising_ATF_Cladding_Materials_in_the_Framework_of_the_Il_Trovatore_Project

Vancouver

Grosse MM, Van Loo K, Frankberg EL, Chonchong T, Lambrinou K, Di Fonzo F et al. Investigation of corrosion an high temperature oxidation of promising ATF cladding materials in the framework of the IL TROVATORE project. In International Nuclear Fuel Cycle Conference and TOP FUEL 2019: Light Water Reactor Fuel Performance conference. ANS - American Nuclear Society. 2019. p. 274-279

Author

Grosse, Mirco M. ; Van Loo, Koba ; Frankberg, Erkka L. ; Chonchong, Tang ; Lambrinou, Konstantza ; Di Fonzo, Fabio ; Steinbrueck, Martin. / Investigation of corrosion an high temperature oxidation of promising ATF cladding materials in the framework of the IL TROVATORE project. International Nuclear Fuel Cycle Conference and TOP FUEL 2019: Light Water Reactor Fuel Performance conference. ANS - American Nuclear Society, 2019. pp. 274-279

Bibtex - Download

@inproceedings{5240300303ab4f4f8747e8131d176613,
title = "Investigation of corrosion an high temperature oxidation of promising ATF cladding materials in the framework of the IL TROVATORE project",
abstract = "The aim of the IL TROVATORE project is the development, characterization and testing of potential materials for nuclear fuel rod claddings with enhanced accident tolerance. One main task of the ongoing investigations are testing of the cladding/coolant interactions under operational as well as accident conditions. A wide range of materials was already tested: oxides, MAX phases, SiC and iron based alloys. The paper gives a rough overview about the results of autoclave tests simulating operational conditions and steam oxidation tests at 1200°C covering transient design basis accident conditions. The results of corrosion tests demonstrates the excellent performance of protective zirconia layers under operational conditions. Whereas chromia shows a low corrosion rate too, the water corrosion of alumina is problematic. The reaction rates obtained for Cr2AlC MAX phase depends strongly on the porosity of the material. Dense material behaves well whereas the corrosion of porous material is fast. The best performance in the steam oxidation tests at 1200°C shows SiC followed by dense Cr2AlC MAX phase, FeCrAl and high entropy alloys. Additional information concerning the reaction rates were obtained by measuring the hydrogen release. For several materials it could be shown that not only processes occur resulting in mass gain but simultaneous reactions take place resulting in a mass loss,",
keywords = "Oxides and silicates, MAX phases, Silicon carbide, Iron based alloys, FeCrAI, Cladding, Fuels",
author = "Grosse, {Mirco M.} and {Van Loo}, Koba and Frankberg, {Erkka L.} and Tang Chonchong and Konstantza Lambrinou and {Di Fonzo}, Fabio and Martin Steinbrueck",
note = "Score=3; 2019 - Global/Top Fuel : Light water reactor fuel performance conference ; Conference date: 22-09-2019 Through 26-09-2019",
year = "2019",
month = sep,
day = "22",
language = "English",
pages = "274--279",
booktitle = "International Nuclear Fuel Cycle Conference and TOP FUEL 2019",
publisher = "ANS - American Nuclear Society",
address = "United States",
url = "http://globaltopfuel.ans.org/",

}

RIS - Download

TY - GEN

T1 - Investigation of corrosion an high temperature oxidation of promising ATF cladding materials in the framework of the IL TROVATORE project

AU - Grosse, Mirco M.

AU - Van Loo, Koba

AU - Frankberg, Erkka L.

AU - Chonchong, Tang

AU - Lambrinou, Konstantza

AU - Di Fonzo, Fabio

AU - Steinbrueck, Martin

N1 - Conference code: 157481

PY - 2019/9/22

Y1 - 2019/9/22

N2 - The aim of the IL TROVATORE project is the development, characterization and testing of potential materials for nuclear fuel rod claddings with enhanced accident tolerance. One main task of the ongoing investigations are testing of the cladding/coolant interactions under operational as well as accident conditions. A wide range of materials was already tested: oxides, MAX phases, SiC and iron based alloys. The paper gives a rough overview about the results of autoclave tests simulating operational conditions and steam oxidation tests at 1200°C covering transient design basis accident conditions. The results of corrosion tests demonstrates the excellent performance of protective zirconia layers under operational conditions. Whereas chromia shows a low corrosion rate too, the water corrosion of alumina is problematic. The reaction rates obtained for Cr2AlC MAX phase depends strongly on the porosity of the material. Dense material behaves well whereas the corrosion of porous material is fast. The best performance in the steam oxidation tests at 1200°C shows SiC followed by dense Cr2AlC MAX phase, FeCrAl and high entropy alloys. Additional information concerning the reaction rates were obtained by measuring the hydrogen release. For several materials it could be shown that not only processes occur resulting in mass gain but simultaneous reactions take place resulting in a mass loss,

AB - The aim of the IL TROVATORE project is the development, characterization and testing of potential materials for nuclear fuel rod claddings with enhanced accident tolerance. One main task of the ongoing investigations are testing of the cladding/coolant interactions under operational as well as accident conditions. A wide range of materials was already tested: oxides, MAX phases, SiC and iron based alloys. The paper gives a rough overview about the results of autoclave tests simulating operational conditions and steam oxidation tests at 1200°C covering transient design basis accident conditions. The results of corrosion tests demonstrates the excellent performance of protective zirconia layers under operational conditions. Whereas chromia shows a low corrosion rate too, the water corrosion of alumina is problematic. The reaction rates obtained for Cr2AlC MAX phase depends strongly on the porosity of the material. Dense material behaves well whereas the corrosion of porous material is fast. The best performance in the steam oxidation tests at 1200°C shows SiC followed by dense Cr2AlC MAX phase, FeCrAl and high entropy alloys. Additional information concerning the reaction rates were obtained by measuring the hydrogen release. For several materials it could be shown that not only processes occur resulting in mass gain but simultaneous reactions take place resulting in a mass loss,

KW - Oxides and silicates

KW - MAX phases

KW - Silicon carbide

KW - Iron based alloys

KW - FeCrAI

KW - Cladding

KW - Fuels

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/38598277

M3 - In-proceedings paper

SP - 274

EP - 279

BT - International Nuclear Fuel Cycle Conference and TOP FUEL 2019

PB - ANS - American Nuclear Society

T2 - 2019 - Global/Top Fuel

Y2 - 22 September 2019 through 26 September 2019

ER -

ID: 6802395