Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT

James O'callaghan; Walter T. Shmayda; Henry Smith; Matthew Sharpe; Lyn Mcwilliam; Philippa Almond; Rhiann Canavan; Nathan Eedy; Gowri Karajgikar; David Kennedy; Hazel Gardner; Fatimah Sanni; Alec Shackleford; Callum Steventon; Josh Ruby; Tshepo Mahafa; David T. Hoelzer; Kalle Heinola; Anthony Hollingsworth

doi:10.1109/TPS.2024.3396645

Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT

James O'callaghan, Walter T. Shmayda, Henry Smith, Matthew Sharpe, Lyn Mcwilliam, Philippa Almond, Rhiann Canavan, Nathan Eedy, Gowri Karajgikar, David Kennedy, Hazel Gardner, Fatimah Sanni, Alec Shackleford, Callum Steventon, Josh Ruby, Tshepo Mahafa, David T. Hoelzer, Kalle Heinola, Anthony Hollingsworth

Alloy Behavior & Design

Research output: Contribution to journal › Article › peer-review

Abstract

Five different candidate structural materials for fusion have undergone pure tritium gas soaking at room temperature and at 310-mbar(a) pressure. The tritium uptake on the surface and in the bulk of the alloys has been analyzed using surface leaching, chemical etching, and thermal desorption. The nickel-based alloys: Inconel-X-750 and Hastelloy-X, absorbed the least amount of total tritium compared with austenitic stainless steel AISI 304L, reduced activation ferritic-martensitic (RAFM) Eurofer-97, and advanced nanoferritic alloy 14YWT. Microstructural analyses using electron backscatter diffraction (EBSD) indicate that the number of grains and mean grain size is not a dominant factor in near surface tritium uptake. The quantity of iron dissolved in the surface oxide appears to be the major factor in encouraging tritium absorption.

Original language	English
Pages (from-to)	3687-3692
Number of pages	6
Journal	IEEE Transactions on Plasma Science
Volume	52
Issue number	9
DOIs	https://doi.org/10.1109/TPS.2024.3396645
State	Published - 2024

Funding

This work was supported in part by the Department for Business, Energy and Industrial Strategy (BEIS) Tactical Fund Memorandum of Understanding (MOU1) and in part by the International Partnerships Fund. The authors would like to thank UR LLE staff for hosting UKAEA scientists at LLE and the UKAEA Materials Science and Engineering Group (MSE) for their support.

Keywords

Stainless steel alloys
XPS
surface inventory
tritium absorption
tritium bulk profiles
tritium solubility

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10.1109/TPS.2024.3396645

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O'callaghan, J., Shmayda, W. T., Smith, H., Sharpe, M., Mcwilliam, L., Almond, P., Canavan, R., Eedy, N., Karajgikar, G., Kennedy, D., Gardner, H., Sanni, F., Shackleford, A., Steventon, C., Ruby, J., Mahafa, T., Hoelzer, D. T., Heinola, K., & Hollingsworth, A. (2024). Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT. IEEE Transactions on Plasma Science, 52(9), 3687-3692. https://doi.org/10.1109/TPS.2024.3396645

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title = "Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT",

abstract = "Five different candidate structural materials for fusion have undergone pure tritium gas soaking at room temperature and at 310-mbar(a) pressure. The tritium uptake on the surface and in the bulk of the alloys has been analyzed using surface leaching, chemical etching, and thermal desorption. The nickel-based alloys: Inconel-X-750 and Hastelloy-X, absorbed the least amount of total tritium compared with austenitic stainless steel AISI 304L, reduced activation ferritic-martensitic (RAFM) Eurofer-97, and advanced nanoferritic alloy 14YWT. Microstructural analyses using electron backscatter diffraction (EBSD) indicate that the number of grains and mean grain size is not a dominant factor in near surface tritium uptake. The quantity of iron dissolved in the surface oxide appears to be the major factor in encouraging tritium absorption.",

keywords = "Stainless steel alloys, XPS, surface inventory, tritium absorption, tritium bulk profiles, tritium solubility",

author = "James O'callaghan and Shmayda, {Walter T.} and Henry Smith and Matthew Sharpe and Lyn Mcwilliam and Philippa Almond and Rhiann Canavan and Nathan Eedy and Gowri Karajgikar and David Kennedy and Hazel Gardner and Fatimah Sanni and Alec Shackleford and Callum Steventon and Josh Ruby and Tshepo Mahafa and Hoelzer, {David T.} and Kalle Heinola and Anthony Hollingsworth",

note = "Publisher Copyright: {\textcopyright} 2024 The Authors.",

year = "2024",

doi = "10.1109/TPS.2024.3396645",

language = "English",

volume = "52",

pages = "3687--3692",

journal = "IEEE Transactions on Plasma Science",

issn = "0093-3813",

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O'callaghan, J, Shmayda, WT, Smith, H, Sharpe, M, Mcwilliam, L, Almond, P, Canavan, R, Eedy, N, Karajgikar, G, Kennedy, D, Gardner, H, Sanni, F, Shackleford, A, Steventon, C, Ruby, J, Mahafa, T, Hoelzer, DT, Heinola, K & Hollingsworth, A 2024, 'Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT', IEEE Transactions on Plasma Science, vol. 52, no. 9, pp. 3687-3692. https://doi.org/10.1109/TPS.2024.3396645

Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT. / O'callaghan, James; Shmayda, Walter T.; Smith, Henry et al.
In: IEEE Transactions on Plasma Science, Vol. 52, No. 9, 2024, p. 3687-3692.

Research output: Contribution to journal › Article › peer-review

TY - JOUR

T1 - Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT

AU - O'callaghan, James

AU - Shmayda, Walter T.

AU - Smith, Henry

AU - Sharpe, Matthew

AU - Mcwilliam, Lyn

AU - Almond, Philippa

AU - Canavan, Rhiann

AU - Eedy, Nathan

AU - Karajgikar, Gowri

AU - Kennedy, David

AU - Gardner, Hazel

AU - Sanni, Fatimah

AU - Shackleford, Alec

AU - Steventon, Callum

AU - Ruby, Josh

AU - Mahafa, Tshepo

AU - Hoelzer, David T.

AU - Heinola, Kalle

AU - Hollingsworth, Anthony

PY - 2024

Y1 - 2024

N2 - Five different candidate structural materials for fusion have undergone pure tritium gas soaking at room temperature and at 310-mbar(a) pressure. The tritium uptake on the surface and in the bulk of the alloys has been analyzed using surface leaching, chemical etching, and thermal desorption. The nickel-based alloys: Inconel-X-750 and Hastelloy-X, absorbed the least amount of total tritium compared with austenitic stainless steel AISI 304L, reduced activation ferritic-martensitic (RAFM) Eurofer-97, and advanced nanoferritic alloy 14YWT. Microstructural analyses using electron backscatter diffraction (EBSD) indicate that the number of grains and mean grain size is not a dominant factor in near surface tritium uptake. The quantity of iron dissolved in the surface oxide appears to be the major factor in encouraging tritium absorption.

AB - Five different candidate structural materials for fusion have undergone pure tritium gas soaking at room temperature and at 310-mbar(a) pressure. The tritium uptake on the surface and in the bulk of the alloys has been analyzed using surface leaching, chemical etching, and thermal desorption. The nickel-based alloys: Inconel-X-750 and Hastelloy-X, absorbed the least amount of total tritium compared with austenitic stainless steel AISI 304L, reduced activation ferritic-martensitic (RAFM) Eurofer-97, and advanced nanoferritic alloy 14YWT. Microstructural analyses using electron backscatter diffraction (EBSD) indicate that the number of grains and mean grain size is not a dominant factor in near surface tritium uptake. The quantity of iron dissolved in the surface oxide appears to be the major factor in encouraging tritium absorption.

KW - Stainless steel alloys

KW - XPS

KW - surface inventory

KW - tritium absorption

KW - tritium bulk profiles

KW - tritium solubility

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U2 - 10.1109/TPS.2024.3396645

DO - 10.1109/TPS.2024.3396645

M3 - Article

AN - SCOPUS:85195374385

SN - 0093-3813

VL - 52

SP - 3687

EP - 3692

JO - IEEE Transactions on Plasma Science

JF - IEEE Transactions on Plasma Science

IS - 9

ER -

Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT

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