pith. machine review for the scientific record. sign in

arxiv: 2604.12612 · v1 · submitted 2026-04-14 · ❄️ cond-mat.mtrl-sci

Recognition: unknown

Damage dose dependence of deuterium retention in high-temperature self-ion irradiated tungsten

Mikhail Zibrov , Thomas Schwarz-Selinger , Michael Klimenkov , Ute J\"antsch
Authors on Pith no claims yet

Pith reviewed 2026-05-10 15:25 UTC · model grok-4.3

classification ❄️ cond-mat.mtrl-sci
keywords tungstendeuterium retentionself-ion irradiationvoidsthermal desorption spectroscopynuclear reaction analysishigh temperature defects
0
0 comments X

The pith

High-temperature self-ion irradiation of tungsten produces nm-sized voids that drive deuterium retention to 1.7 at.% at 2.3 dpa with no saturation.

A machine-rendered reading of the paper's core claim, the machinery that carries it, and where it could break.

The paper examines how tungsten irradiated at 1350 K retains deuterium after plasma exposure, contrasting the behavior with samples irradiated at 290 K and 800 K. At low damage doses below 0.1 dpa the trapped deuterium is lower than in the 800 K case, but at higher doses it rises above those values and reaches 1.7 atomic percent at the maximum dose of 2.3 dpa without any sign of leveling off. Transmission electron microscopy shows that only the 1350 K irradiation creates nanometer-scale voids, while thermal desorption spectra indicate a new dominant trapping mechanism. Reaction-diffusion modeling reproduces the desorption spectra when deuterium is placed as D2 gas inside the voids and as atoms bound to the void surfaces. These observations establish that the defect population formed at high temperature changes the dose dependence of retention.

Core claim

Recrystallized tungsten irradiated at 1350 K to peak damage doses of 0.001-2.3 dpa develops nm-sized voids visible by transmission electron microscopy. After low-energy deuterium plasma exposure at 370 K the maximum trapped deuterium concentration is lower than after 800 K irradiation for doses below 0.1 dpa, but exceeds it at higher doses and reaches 1.7 at.% at 2.3 dpa with no saturation. Thermal desorption spectra differ from those obtained after lower-temperature irradiations, and reaction-diffusion simulations account for the spectra by trapping deuterium as D2 molecules inside the void volume and as D atoms at the void surfaces.

What carries the argument

nm-sized voids that trap deuterium as D2 gas in their interior volume and as D atoms on their surfaces, modeled by reaction-diffusion simulations to match the measured thermal desorption spectra.

If this is right

  • Deuterium retention in high-temperature-irradiated tungsten increases with damage dose beyond the levels seen after 800 K irradiation.
  • The dominant trapping sites shift from those present at lower irradiation temperatures to the surfaces and interiors of the nm voids.
  • Thermal desorption spectra can be reproduced by assuming D2 gas inside voids and D atoms on void surfaces without invoking additional trap types.
  • Retention shows no saturation up to at least 2.3 dpa, implying continued growth of the void population or their trapping capacity.

Where Pith is reading between the lines

These are editorial extensions of the paper, not claims the author makes directly.

  • If the same void-based trapping operates in fusion reactor walls, tritium inventory estimates for high-temperature regions may need upward revision at high neutron doses.
  • The transition from lower to higher retention occurs between 0.1 and 2.3 dpa, suggesting a critical damage threshold at which voids become the controlling defect.
  • Extending the irradiation temperature or dose range could test whether void growth eventually leads to blistering or other macroscopic surface changes.

Load-bearing premise

The nm-sized voids seen in TEM are the main reason for the changed retention behavior and that no other irradiation-induced defects contribute substantially to trapping.

What would settle it

Measuring deuterium retention and performing TEM on samples irradiated at 1350 K to doses above 2.3 dpa to check whether the concentration continues to rise or finally saturates, or finding additional defect types that trap deuterium outside the voids.

Figures

Figures reproduced from arXiv: 2604.12612 by Michael Klimenkov, Mikhail Zibrov, Thomas Schwarz-Selinger, Ute J\"antsch.

Figure 1
Figure 1. Figure 1: TEM images and the corresponding void size distribution histograms for W [PITH_FULL_IMAGE:figures/full_fig_p007_1.png] view at source ↗
Figure 2
Figure 2. Figure 2: (a) TEM image showing the void distribution over the sample thickness in [PITH_FULL_IMAGE:figures/full_fig_p008_2.png] view at source ↗
Figure 3
Figure 3. Figure 3: D concentration profiles in W irradiated with 20 MeV W ions at 1350 K to the [PITH_FULL_IMAGE:figures/full_fig_p009_3.png] view at source ↗
Figure 4
Figure 4. Figure 4: D concentration profiles in W irradiated with 20 MeV W ions at 1350 K to [PITH_FULL_IMAGE:figures/full_fig_p010_4.png] view at source ↗
Figure 5
Figure 5. Figure 5: Maximum trapped D concentration as a function of the peak damage dose in W [PITH_FULL_IMAGE:figures/full_fig_p011_5.png] view at source ↗
Figure 6
Figure 6. Figure 6: Maximum trapped D concentration as a function of the ion irradiation temper [PITH_FULL_IMAGE:figures/full_fig_p012_6.png] view at source ↗
Figure 7
Figure 7. Figure 7: TDS spectra from W irradiated with 20 MeV W ions at 1350 K to various peak [PITH_FULL_IMAGE:figures/full_fig_p013_7.png] view at source ↗
Figure 8
Figure 8. Figure 8: Comparison of experimental and simulated D concentration profiles for the [PITH_FULL_IMAGE:figures/full_fig_p016_8.png] view at source ↗
Figure 9
Figure 9. Figure 9: Comparison of experimental and simulated TDS spectra from the samples irra [PITH_FULL_IMAGE:figures/full_fig_p017_9.png] view at source ↗
Figure 10
Figure 10. Figure 10: Schematic potential energy diagram for H atoms (solid line) and H [PITH_FULL_IMAGE:figures/full_fig_p021_10.png] view at source ↗
read the original abstract

Recrystallized tungsten (W) samples were irradiated by 20 MeV self-ions at 1350 K to peak damage doses in the range of 0.001-2.3 dpa. The irradiation-induced defects were then decorated with deuterium (D) by a gentle D plasma exposure ($<5$ eV/D, $5.6 \times 10^{19}$ $\text{D} / (\text{m}^2 \text{s})$) at 370 K. The D depth profiles in the samples were measured using $\rm D(^{3}He,p)\alpha$ nuclear reaction analysis. The maximum trapped D concentration evolves differently with the damage dose compared with the previously studied irradiations at 290 K and 800 K. At the damage doses below 0.1 dpa, the D concentrations are lower than those after the irradiation at 800 K. At higher damage doses, the D concentrations exceed the 800 K values and reach 1.7 at.% at 2.3 dpa, showing no clear tendency towards saturation. Transmission electron microscopy revealed the presence of nm-sized voids in the samples irradiated at 1350 K, in contrast to the ones irradiated at 290 K and 800 K. Thermal desorption spectroscopy (TDS) indicates that the dominant D trapping sites are different compared to the irradiations at 290 K and 800 K. Reaction-diffusion simulations show that the TDS spectra can be described by assuming that D is trapped as $\rm D_2$ gas in the void volume and as D atoms at the void surface.

Editorial analysis

A structured set of objections, weighed in public.

Desk editor's note, referee report, simulated authors' rebuttal, and a circularity audit. Tearing a paper down is the easy half of reading it; the pith above is the substance, this is the friction.

Referee Report

3 major / 2 minor

Summary. The manuscript reports experimental results on deuterium retention in recrystallized tungsten irradiated with 20 MeV self-ions at 1350 K to peak damage doses of 0.001–2.3 dpa, followed by low-energy D plasma exposure at 370 K. NRA depth profiling shows that D concentrations are lower than in prior 800 K irradiations below 0.1 dpa but exceed them at higher doses, reaching 1.7 at.% at 2.3 dpa with no saturation. TEM reveals nm-sized voids only in the 1350 K samples, and TDS spectra are reproduced by reaction-diffusion simulations assuming D2 gas in void volumes plus D atoms on void surfaces.

Significance. If the void-based trapping interpretation holds after quantitative validation, the work identifies a distinct high-temperature regime for defect evolution and D retention in W that differs from lower-temperature behavior, with direct relevance to tritium inventory predictions in fusion divertor materials.

major comments (3)
  1. [Abstract, TEM results, and reaction-diffusion simulations] The central claim that D retention reaches 1.7 at.% at 2.3 dpa with no saturation and is dominated by voids requires a forward calculation from the TEM-observed void number density and size distribution to the measured D inventory (via ideal-gas D2 pressure at the observed TDS release temperature plus surface coverage); this link is not provided in the results or simulation sections.
  2. [NRA profiling and dose-dependence results] The NRA-derived D concentrations versus dose lack reported error bars, uncertainties from counting statistics or depth resolution, and details on replicate measurements, which weakens the assertion of a clear crossover above 0.1 dpa and the lack of saturation.
  3. [TDS and simulations] The reaction-diffusion model reproduces TDS spectra under the void-trapping assumption, but the manuscript does not report whether alternative defect populations (e.g., dislocation loops or sub-TEM vacancy clusters) were tested or ruled out, nor the goodness-of-fit metrics or free-parameter values used.
minor comments (2)
  1. [Experimental methods] The D plasma exposure is specified by flux but the total fluence or exposure duration should be stated explicitly in the methods for reproducibility.
  2. [Figures] Figures showing NRA profiles and TDS spectra would be clearer with raw data points, error bars, and direct overlays of the simulation fits.

Simulated Author's Rebuttal

3 responses · 0 unresolved

We thank the referee for the constructive and detailed comments, which help improve the clarity and rigor of our manuscript. We address each major comment point by point below, indicating where revisions will be made.

read point-by-point responses

  1. Referee: [Abstract, TEM results, and reaction-diffusion simulations] The central claim that D retention reaches 1.7 at.% at 2.3 dpa with no saturation and is dominated by voids requires a forward calculation from the TEM-observed void number density and size distribution to the measured D inventory (via ideal-gas D2 pressure at the observed TDS release temperature plus surface coverage); this link is not provided in the results or simulation sections.

    Authors: We agree that a quantitative forward calculation linking the TEM-observed void number density and size distribution to the NRA-measured D inventory would strengthen the central claim. In the revised manuscript, we will add this calculation in the results or discussion section. It will estimate the trapped deuterium from D2 gas (using the ideal gas law at the TDS release temperature) plus surface-bound D atoms (assuming monolayer coverage) and compare the result directly to the observed retention of 1.7 at.% at 2.3 dpa. revision: yes

  2. Referee: [NRA profiling and dose-dependence results] The NRA-derived D concentrations versus dose lack reported error bars, uncertainties from counting statistics or depth resolution, and details on replicate measurements, which weakens the assertion of a clear crossover above 0.1 dpa and the lack of saturation.

    Authors: We acknowledge that error bars, uncertainty details, and replicate information were omitted from the original submission. In the revised manuscript, we will add error bars to the D concentration versus dose plot, derived from counting statistics in the NRA measurements and depth resolution considerations. We will also include a statement on the number of replicate samples measured at each dose to support the reported crossover above 0.1 dpa and the absence of saturation up to 2.3 dpa. revision: yes

  3. Referee: [TDS and simulations] The reaction-diffusion model reproduces TDS spectra under the void-trapping assumption, but the manuscript does not report whether alternative defect populations (e.g., dislocation loops or sub-TEM vacancy clusters) were tested or ruled out, nor the goodness-of-fit metrics or free-parameter values used.

    Authors: We will revise the simulation section to report the specific free-parameter values used in the reaction-diffusion model and include quantitative goodness-of-fit metrics (e.g., reduced chi-squared) for the agreement with experimental TDS spectra. Regarding alternatives, the model is grounded in the TEM observation of nm-sized voids as the primary defect at 1350 K; we will add a discussion noting that other populations such as dislocation loops or sub-TEM clusters were not explicitly simulated but are expected to be less dominant based on the high-temperature release peak and dose dependence. This addresses the reporting gap while remaining consistent with the data presented. revision: partial

Circularity Check

0 steps flagged

No significant circularity; experimental results and model fits are independent of self-defined inputs

full rationale

The paper reports direct experimental measurements (NRA depth profiles, TDS spectra, TEM void observations) of D retention as a function of damage dose at 1350 K. The reaction-diffusion simulations are presented only as a descriptive fit ('can be described by assuming' D2 gas in voids plus surface atoms), with no equations or parameters shown to reduce the reported 1.7 at.% concentration or TDS peaks to quantities defined solely by prior fits from the same authors. Prior-temperature comparisons supply context but carry no load-bearing uniqueness theorem or ansatz that forces the current conclusions. The chain remains self-contained against external benchmarks.

Axiom & Free-Parameter Ledger

1 free parameters · 1 axioms · 0 invented entities

The interpretation of non-saturating retention and TDS spectra rests on the assumption that nm voids are the primary new defect type and that a reaction-diffusion model with only two trapping modes (D2 gas in void volume, atomic D on surfaces) is sufficient.

free parameters (1)
  • void trapping energies and densities
    Parameters in the reaction-diffusion simulations adjusted to reproduce the measured TDS spectra.
axioms (1)
  • domain assumption D trapping occurs primarily as D2 gas inside voids and atomic D on void surfaces
    Invoked to explain why the TDS spectra differ from lower-temperature cases and to fit the data.

pith-pipeline@v0.9.0 · 5607 in / 1501 out tokens · 33337 ms · 2026-05-10T15:25:29.230686+00:00 · methodology

discussion (0)

Sign in with ORCID, Apple, or X to comment. Anyone can read and Pith papers without signing in.

Reference graph

Works this paper leans on

77 extracted references · 63 canonical work pages

  1. [1]

    Federici, W

    G. Federici, W. Biel, M. Gilbert, R. Kemp, N. Taylor, R. Wenninger, European demo design strategy and consequences for materials, Nuclear Fusion 57 (9) (2017) 092002.doi:10.1088/1741-4326/57/9/092002. 23 W density ρ 6.306×10 28 at./m3 Jump distance between near- est interstitial sites λ 1.12×10 −10 m Number of interstitial sites per lattice atom h 6 Diffu...

    work page doi:10.1088/1741-4326/57/9/092002 2017

  2. [2]

    Y. Ueda, K. Schmid, M. Balden, J. Coenen, T. Loewenhoff, A. Ito, A. Hasegawa, C. Hardie, M. Porton, M. Gilbert, Baseline high heat flux and plasma facing materials for fusion, Nuclear Fusion 57 (9) (2017) 092006.doi:10.1088/1741-4326/aa6b60

    work page doi:10.1088/1741-4326/aa6b60 2017

  3. [3]

    fireplace

    S. J. Zinkle, A. Quadling, Extreme materials environment of the fusion 24 “fireplace”, MRS Bulletin 47 (11) (2022) 1113–1119.doi:10.1557/ s43577-022-00453-9

    2022

  4. [4]

    S. J. Zinkle, 1.04 - radiation-induced effects on microstructure, in: R. J. Konings, R. E. Stoller (Eds.), Comprehensive Nuclear Materials (Second Edition), Elsevier, Oxford, 2020, pp. 91–129.doi:10.1016/ B978-0-12-803581-8.12075-2

    2020

  5. [5]

    Bhattacharya, S

    A. Bhattacharya, S. J. Zinkle, 1.12 - cavity swelling in irradiated ma- terials, in: R. J. Konings, R. E. Stoller (Eds.), Comprehensive Nu- clear Materials (Second Edition), Elsevier, Oxford, 2020, pp. 406–455. doi:10.1016/B978-0-12-803581-8.11599-1

    work page doi:10.1016/b978-0-12-803581-8.11599-1 2020

  6. [6]

    Hu, Recent progress in experimental investigation of neutron irra- diation response of tungsten, Journal of Nuclear Materials 568 (2022) 153856.doi:10.1016/j.jnucmat.2022.153856

    X. Hu, Recent progress in experimental investigation of neutron irra- diation response of tungsten, Journal of Nuclear Materials 568 (2022) 153856.doi:10.1016/j.jnucmat.2022.153856

    work page doi:10.1016/j.jnucmat.2022.153856 2022

  7. [7]

    G. S. Was, S. J. Zinkle, 1.14 - Toward the Use of Ion Irradiation to Predict Reactor Irradiation Effects, in: R. J. Konings, R. E. Stoller (Eds.), Comprehensive Nuclear Materials (Second Edition), Elsevier, Oxford, 2020.doi:10.1016/B978-0-12-803581-8.12053-3

    work page doi:10.1016/b978-0-12-803581-8.12053-3 2020

  8. [8]

    Boleininger, D

    M. Boleininger, D. R. Mason, T. Schwarz-Selinger, P.-W. Ma, Atomistic simulations of irradiation damage on the engineering timescale: exam- ining the dose rate effect in tungsten, Mater. Adv. 6 (2025) 7379–7394. doi:10.1039/D5MA00677E

    work page doi:10.1039/d5ma00677e 2025

  9. [9]

    Zhao, Y.-H

    W. Zhao, Y.-H. Li, H.-Z. Ma, Y.-Z. Niu, Z. Yang, D. Terentyev, H.-B. Zhou, G.-H. Lu, Dependence of irradiation defects evolution on dose rate and pka energy spectrum in tungsten, Nuclear Materials and Energy 43 (2025) 101956.doi:10.1016/j.nme.2025.101956

    work page doi:10.1016/j.nme.2025.101956 2025

  10. [10]

    T. Schwarz-Selinger, A critical review of experiments on deuterium retention in displacement-damaged tungsten as function of damaging dose, Materials Research Express 10 (2023) 102002.doi:10.1088/ 2053-1591/acfdf8

    2023

  11. [11]

    D. R. Mason, F. Granberg, M. Boleininger, T. Schwarz-Selinger, K. Nordlund, S. L. Dudarev, Parameter-free quantitative simula- tion of high-dose microstructure and hydrogen retention in ion- 25 irradiated tungsten, Phys. Rev. Mater. 5 (2021) 095403.doi:10.1103/ PhysRevMaterials.5.095403

    2021

  12. [12]

    Boleininger, D

    M. Boleininger, D. R. Mason, A. E. Sand, S. L. Dudarev, Microstructure of a heavily irradiated metal exposed to a spectrum of atomic recoils, Sci- entific Reports 13 (1) (2023) 1684.doi:10.1038/s41598-022-27087-w

    work page doi:10.1038/s41598-022-27087-w 2023

  13. [13]

    Hollingsworth, M.-F

    A. Hollingsworth, M.-F. Barthe, M. Y. Lavrentiev, P. Derlet, S. Du- darev, D. Mason, Z. Hu, P. Desgardin, J. Hess, S. Davies, B. Thomas, H. Salter, E. Shelton, K. Heinola, K. Mizohata, A. De Backer, A. Baron- Wiechec, I. Jepu, Y. Zayachuk, A. Widdowson, E. Meslin, A. Morellec, Comparative study of deuterium retention and vacancy content of self- ion irrad...

    work page doi:10.1016/j.jnucmat.2021.153373 2022

  14. [14]

    Wielu´ nska-Ku´ s, M

    B. Wielu´ nska-Ku´ s, M. Dickmann, W. Egger, M. Zibrov, L. Ciupi´ nski, Positron lifetime study of ion-irradiated tungsten: Ion type and dose effects, Nuclear Materials and Energy 38 (2024) 101610.doi:10.1016/ j.nme.2024.101610

    work page arXiv 2024

  15. [15]

    A. Reza, H. Yu, K. Mizohata, F. Hofmann, Thermal diffusivity degrada- tion and point defect density in self-ion implanted tungsten, Acta Ma- terialia 193 (2020) 270–279.doi:10.1016/j.actamat.2020.03.034

    work page doi:10.1016/j.actamat.2020.03.034 2020

  16. [16]

    Klimenkov, M

    M. Klimenkov, M. D¨ urrschnabel, U. J¨ antsch, P. Lied, M. Rieth, H. Schneider, D. Terentyev, W. Van Renterghem, Microstructural anal- ysis of W irradiated at different temperatures, Journal of Nuclear Ma- terials 572 (2022) 154018.doi:10.1016/j.jnucmat.2022.154018

    work page doi:10.1016/j.jnucmat.2022.154018 2022

  17. [17]

    Klimenkov, U

    M. Klimenkov, U. J¨ antsch, M. Rieth, H. Schneider, D. Terentyev, W. Van Renterghem, Influence of transmutation-induced Re/Os con- tent on defect evolution in neutron-irradiated W, Journal of Nuclear Materials 592 (2024) 154950.doi:10.1016/j.jnucmat.2024.154950

    work page doi:10.1016/j.jnucmat.2024.154950 2024

  18. [18]

    Klimenkov, U

    M. Klimenkov, U. J¨ antsch, M. Rieth, H. Schneider, D. Terentyev, W. Van Renterghem, Effect of irradiation parameters on defect evo- lution in neutron irradiated tungsten, Journal of Nuclear Materials 607 (2025) 155673.doi:10.1016/j.jnucmat.2025.155673. 26

    work page doi:10.1016/j.jnucmat.2025.155673 2025

  19. [19]

    S. Wang, H. Wang, X. Yi, W. Tan, L. Ge, Y. Sun, W. Guo, Q. Yang, L. Cheng, X. Zhang, Y. Yuan, X. Cao, E. Fu, G.-H. Lu, Damage recov- ery stages revisited: Thermal evolution of non-saturated and saturated displacement damage in heavy-ion irradiated tungsten, Acta Materialia 273 (2024) 119942.doi:10.1016/j.actamat.2024.119942

    work page doi:10.1016/j.actamat.2024.119942 2024

  20. [20]

    S. Wang, H. Wang, W. Tan, X. Yi, Z. Hu, T. Schwarz-Selinger, D. R. Mason, M.-F. Barthe, P. Desgardin, S. Shen, L. Cheng, X. Zhang, Y. Yuan, E. Fu, G.-H. Lu, Displacement damage saturation in tung- sten at elevated temperatures, Acta Materialia 310 (2026) 122148. doi:10.1016/j.actamat.2026.122148

    work page doi:10.1016/j.actamat.2026.122148 2026

  21. [21]

    Hou, X.-S

    J. Hou, X.-S. Kong, X. Wu, J. Song, C. S. Liu, Predictive model of hydrogen trapping and bubbling in nanovoids in bcc metals, Nature Materials 18 (2019) 833–839.doi:10.1038/s41563-019-0422-4

    work page doi:10.1038/s41563-019-0422-4 2019

  22. [22]

    Ren, Y.-H

    Q.-Y. Ren, Y.-H. Li, H.-B. Zhou, Z.-Z. Li, L. Cheng, G.-H. Lu, Char- acterization of the energetics and configurations of hydrogen in va- cancy clusters in tungsten, Nuclear Fusion 59 (10) (2019) 106032. doi:10.1088/1741-4326/ab36a4

    work page doi:10.1088/1741-4326/ab36a4 2019

  23. [23]

    Van Veen, H

    A. Van Veen, H. Filius, J. De Vries, K. Bijkerk, G. Rozing, D. Segers, Hydrogen exchange with voids in tungsten observed with TDS and PA, Journal of Nuclear Materials 155-157 (1988) 1113–1117.doi:10.1016/ 0022-3115(88)90478-3

    1988

  24. [25]

    Zibrov, K

    M. Zibrov, K. Schmid, Reaction–diffusion simulations of hydrogen iso- tope trapping and release from cavities in tungsten, II: Array of cavities, Nuclear Materials and Energy 32 (2022) 101219.doi:10.1016/j.nme. 2022.101219

    work page doi:10.1016/j.nme 2022

  25. [26]

    Ogorodnikova, Y

    O. Ogorodnikova, Y. Gasparyan, V. Efimov, L. Ciupi´ nski, J. Grzonka, Annealing of radiation-induced damage in tungsten under and after ir- radiation with 20 MeV self-ions, Journal of Nuclear Materials 451 (2014) 379 – 386.doi:10.1016/j.jnucmat.2014.04.011. 27

    work page doi:10.1016/j.jnucmat.2014.04.011 2014

  26. [27]

    Sakurada, K

    S. Sakurada, K. Yuyama, Y. Uemura, H. Fujita, C. Hu, T. Toyama, N. Yoshida, T. Hinoki, S. Kondo, M. Shimada, D. Buchenauer, T. Chikada, Y. Oya, Annealing effects on deuterium retention behavior in damaged tungsten, Nuclear Materials and Energy 9 (2016) 141–144. doi:10.1016/j.nme.2016.06.012

    work page doi:10.1016/j.nme.2016.06.012 2016

  27. [28]

    Simmonds, Y

    M. Simmonds, Y. Wang, J. Barton, M. Baldwin, J. Yu, R. Doerner, G. Tynan, Reduced deuterium retention in simultaneously damaged and annealed tungsten, Journal of Nuclear Materials 494 (2017) 67–71.doi: 10.1016/j.jnucmat.2017.06.010

    work page doi:10.1016/j.jnucmat.2017.06.010 2017

  28. [29]

    Markelj, T

    S. Markelj, T. Schwarz-Selinger, M. Peˇ covnik, A. Zaloˇ znik, M. Kelemen, I. ˇCadeˇ z, J. Bauer, P. Pelicon, W. Chromi´ nski, L. Ciupinski, Displace- ment damage stabilization by hydrogen presence under simultaneous W ion damage and D ion exposure, Nuclear Fusion 59 (8) (2019) 086050. doi:10.1088/1741-4326/ab2261

    work page doi:10.1088/1741-4326/ab2261 2019

  29. [30]

    Kobayashi, M

    M. Kobayashi, M. Shimada, C. N. Taylor, D. Buchenauer, R. Kolasin- ski, T. Koyanagi, Y. Nobuta, Y. Hatano, Y. Oya, Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron, Fusion Engineering and Design 146 (2019) 1624–1627.doi:10.1016/j.fusengdes.2019.03.003

    work page doi:10.1016/j.fusengdes.2019.03.003 2019

  30. [31]

    J. Wang, Y. Hatano, T. Hinoki, V. K. Alimov, A. V. Spitsyn, N. P. Bobyr, S. Kondo, T. Toyama, H. T. Lee, Y. Ueda, T. Schwarz-Selinger, Deuterium retention in W and binary W alloys irradiated with high energy Fe ions, Journal of Nuclear Materials 545 (2021) 152749.doi: 10.1016/j.jnucmat.2020.152749

    work page doi:10.1016/j.jnucmat.2020.152749 2021

  31. [32]

    Markelj, M

    S. Markelj, M. Peˇ covnik, T. Schwarz-Selinger, M. Kelemen, The syner- gies between displacement damage creation and hydrogen presence: the effect of D ion energy and flux, Physica Scripta 97 (2) (2022) 024006. doi:10.1088/1402-4896/ac4860

    work page doi:10.1088/1402-4896/ac4860 2022

  32. [33]

    Zhu, Z.-H

    X.-L. Zhu, Z.-H. Ke, L. Cheng, P. Zhang, Y. Yuan, X.-Z. Cao, G.-H. Lu, The effect of high-temperature pre-damage on vacancy-type defects and deuterium retention in tungsten, Nuclear Materials and Energy 38 (2024) 101620.doi:10.1016/j.nme.2024.101620. 28

    work page doi:10.1016/j.nme.2024.101620 2024

  33. [34]

    M. Oya, M. Shimada, C. Taylor, M. Kobayashi, Y. Nobuta, Y. Ya- mauchi, Y. Oya, Y. Ueda, Y. Hatano, Deuterium retention in tungsten irradiated by high-dose neutrons at high temperature, Nuclear Materials and Energy 27 (2021) 100980.doi:10.1016/j.nme.2021.100980

    work page doi:10.1016/j.nme.2021.100980 2021

  34. [35]

    Schwarz-Selinger, Unpublished data

    T. Schwarz-Selinger, Unpublished data. Partially presented in: irradia- tions at 290 K [D. R. Mason et al., Phys. Rev. Mater. 5 (2021) 095403]; irradiations at 800 K [J. Dark et al., Nucl. Fusion 64 (2024) 086026] and [M. Boleininger et al, Mater. Adv. 6 (2025) 7379]

    2021

  35. [36]

    Chrominski, L

    W. Chrominski, L. Ciupinski, P. Bazarnik, S. Markelj, T. Schwarz- Selinger, TEM investigation of the influence of dose rate on radiation damage and deuterium retention in tungsten, Materials Characteriza- tion 154 (2019) 1–6.doi:10.1016/j.matchar.2019.05.028

    work page doi:10.1016/j.matchar.2019.05.028 2019

  36. [37]

    Zibrov, A

    M. Zibrov, A. Cintora, T. Schwarz-Selinger, K. Hunger, M. Mayer, N. Bobyr, Deuterium retention in displacement-damaged tungsten- rhenium alloys: Influence of rhenium concentration and irradiation temperature, Nuclear Materials and Energy 41 (2024) 101730.doi: 10.1016/j.nme.2024.101730

    work page doi:10.1016/j.nme.2024.101730 2024

  37. [38]

    Manhard, G

    A. Manhard, G. Matern, M. Balden, A step-by-step analysis of the pol- ishing process for tungsten specimens, Practical Metallography 50 (1) (2013) 5–16.doi:10.3139/147.110215

    work page doi:10.3139/147.110215 2013

  38. [39]

    Manhard, M

    A. Manhard, M. Balden, S. Elgeti, Quantitative microstructure and de- fect density analysis of polycrystalline tungsten reference samples after different heat treatments, Practical Metallography 52 (8) (2015) 437– 466.doi:10.3139/147.110354

    work page doi:10.3139/147.110354 2015

  39. [40]

    T. Schwarz-Selinger, Deuterium retention in MeV self-implanted tung- sten: Influence of damaging dose rate, Nuclear Materials and Energy 12 (2017) 683 – 688.doi:10.1016/j.nme.2017.02.003

    work page doi:10.1016/j.nme.2017.02.003 2017

  40. [41]

    G. Was, S. Taller, Z. Jiao, A. Monterrosa, D. Woodley, D. Jennings, T. Kubley, F. Naab, O. Toader, E. Uberseder, Resolution of the carbon contamination problem in ion irradiation experiments, Nuclear Instru- ments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 412 (2017) 58–65.doi:10.1016/j.nimb. 2017.08.039. 29

    work page doi:10.1016/j.nimb 2017

  41. [43]

    Guitart Corominas, T

    M. Guitart Corominas, T. Schwarz-Selinger, Experimental determina- tion of the 16o(3he,p0)18f differential cross section, Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Ma- terials and Atoms 450 (2019) 13–18.doi:10.1016/j.nimb.2018.05. 018

    work page doi:10.1016/j.nimb.2018.05 2019

  42. [44]

    J. F. Ziegler, J. P. Biersack, M. D. Ziegler, SRIM - The Stopping and Range of Ions in Matter, www.srim.org

  43. [45]

    ASTM E521-16, Standard Practice for Investigating the Effects of Neu- tron Radiation Damage Using Charged-Particle Irradiation, ASTM In- ternational, West Conshohocken, PA, USA, 2016, www.astm.org.doi: 10.1520/E0521-16

    work page doi:10.1520/e0521-16 2016

  44. [46]

    Stoller, M

    R. Stoller, M. Toloczko, G. Was, A. Certain, S. Dwaraknath, F. Garner, On the use of SRIM for computing radiation damage exposure, Nuclear Instruments and Methods in Physics Research Section B 310 (2013) 75 – 80.doi:10.1016/j.nimb.2013.05.008

    work page doi:10.1016/j.nimb.2013.05.008 2013

  45. [47]

    Manhard, T

    A. Manhard, T. Schwarz-Selinger, W. Jacob, Quantification of the deu- terium ion fluxes from a plasma source, Plasma Sources Science and Technology 20 (2011) 015010.doi:10.1088/0963-0252/20/1/015010

    work page doi:10.1088/0963-0252/20/1/015010 2011

  46. [48]

    Mayer, E

    M. Mayer, E. Gauthier, K. Sugiyama, U. von Toussaint, Quantitative depth profiling of deuterium up to very large depths, Nuclear Instru- ments and Methods in Physics Research Section B 267 (2009) 506 – 512.doi:10.1016/j.nimb.2008.11.033

    work page doi:10.1016/j.nimb.2008.11.033 2009

  47. [49]

    Schmid, U

    K. Schmid, U. von Toussaint, Statistically sound evaluation of trace element depth profiles by ion beam analysis, Nuclear Instruments and Methods in Physics Research Section B 281 (2012) 64 – 71.doi:10. 1016/j.nimb.2012.03.024

    2012

  48. [50]

    Mayer, SIMNRA user’s guide, Tech

    M. Mayer, SIMNRA user’s guide, Tech. Rep. IPP 9/113 (1997). URLhttp://home.mpcdf.mpg.de/ ~mam/Report%20IPP%209-113.pdf 30

    1997

  49. [51]

    Wielunska, M

    B. Wielunska, M. Mayer, T. Schwarz-Selinger, U. von Toussaint, J. Bauer, Cross section data for the D( 3He,p) 4He nuclear reaction from 0.25 to 6 MeV, Nuclear Instruments and Methods in Physics Research Section B 371 (2016) 41 – 45.doi:10.1016/j.nimb.2015.09.049

    work page doi:10.1016/j.nimb.2015.09.049 2016

  50. [52]

    M¨ oller, F

    W. M¨ oller, F. Besenbacher, A note on the 3He + D nuclear-reaction cross section, Nuclear Instruments and Methods 168 (1) (1980) 111– 114.doi:10.1016/0029-554X(80)91239-2

    work page doi:10.1016/0029-554x(80)91239-2 1980

  51. [53]

    Haesevoets, B

    T. Schwarz-Selinger, T. D¨ urbeck, A. Manhard, In-situ water signal cali- bration method for thermal desorption spectroscopy, Nuclear Materials and Energy 45 (2025) 102029.doi:10.1016/j.nme.2025.102029

    work page doi:10.1016/j.nme.2025.102029 2025

  52. [54]

    S. Wang, H. Wang, X. Yi, Y. Sun, S. Shen, W. Guo, Q. Yang, L. Cheng, Y. Yuan, X. Cao, E. Fu, G.-H. Lu, A combinatorial scheme to tai- lor saturated displacement damage in heavy-ion irradiated tungsten via post-irradiation annealing, Nuclear Fusion 66 (5) (2026) 056015. doi:10.1088/1741-4326/ae4fe2

    work page doi:10.1088/1741-4326/ae4fe2 2026

  53. [55]

    Horv´ ath, R

    B. Horv´ ath, R. Sch¨ aublin, Y. Dai, Flash electropolishing of tem lamellas of irradiated tungsten, Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 449 (2019) 29–34.doi:10.1016/j.nimb.2019.04.047

    work page doi:10.1016/j.nimb.2019.04.047 2019

  54. [56]

    L. Shao, Z. Hu, A. French, Y. Li, Y. Hong, F. A. Garner, Origin of sub- surface swelling peaks in ion irradiation and their mitigation through dose rate control, Materials Today Communications 48 (2025) 113553. doi:10.1016/j.mtcomm.2025.113553

    work page doi:10.1016/j.mtcomm.2025.113553 2025

  55. [57]

    Agnoli, Kinetics of deuterium uptake in self-ion irradiated tungsten at different temperatures, Tech

    D. Agnoli, Kinetics of deuterium uptake in self-ion irradiated tungsten at different temperatures, Tech. Rep. IPP 2026-07, Max-Planck-Institut f¨ ur Plasmaphysik, Garching (2026).doi:10.17617/2.3697177

    work page doi:10.17617/2.3697177 2026

  56. [58]

    Z. Hu, P. Desgardin, C. Genevois, J. Joseph, B. D´ ecamps, R. Sch¨ aublin, M.-F. Barthe, Effect of purity on the vacancy defects induced in self–irradiated tungsten: A combination of pas and tem, Journal of Nuclear Materials 556 (2021) 153175.doi:10.1016/j.jnucmat.2021. 153175. 31

    work page doi:10.1016/j.jnucmat.2021 2021

  57. [59]

    Zavaˇ snik, A

    J. Zavaˇ snik, A. ˇSestan, T. Schwarz-Selinger, K. Hunger, E. Lu, F. Tuomisto, K. Nordlund, E. Punz´ on-Quijorna, M. Kelemen, J. Pre- drag, M. Crespillo, G. G. L´ opez, P. Zhang, X. Cao, S. Markelj, Mi- crostructural analysis of tungsten single crystals irradiated by mev w ions: The effect of irradiation dose and temperature, Materials Charac- terization ...

    work page doi:10.1016/j.matchar.2025.115050 2025

  58. [60]

    Getto, Z

    E. Getto, Z. Jiao, A. Monterrosa, K. Sun, G. Was, Effect of ir- radiation mode on the microstructure of self-ion irradiated ferritic- martensitic alloys, Journal of Nuclear Materials 465 (2015) 116–126. doi:10.1016/j.jnucmat.2015.05.016

    work page doi:10.1016/j.jnucmat.2015.05.016 2015

  59. [61]

    J. G. Gigax, E. Aydogan, T. Chen, D. Chen, L. Shao, Y. Wu, W. Lo, Y. Yang, F. Garner, The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450°C, Journal of Nuclear Materials 465 (2015) 343–348.doi:10.1016/j.jnucmat.2015.05.025

    work page doi:10.1016/j.jnucmat.2015.05.025 2015

  60. [62]

    Kapser, M

    S. Kapser, M. Balden, T. F. da Silva, S. Elgeti, A. Manhard, K. Schmid, T. Schwarz-Selinger, U. von Toussaint, Influence of sub- surface damage evolution on low-energy-plasma-driven deuterium per- meation through tungsten, Nuclear Fusion 58 (5) (2018) 056027.doi: 10.1088/1741-4326/aab571

    work page doi:10.1088/1741-4326/aab571 2018

  61. [63]

    Takagi, Diffusive Behaviors of Deuterium in Nickel under Irradiation of Helium-3, Journal of Nuclear Science and Technology 29 (10) (1992) 947–956.doi:10.1080/18811248.1992.9731618

    I. Takagi, Diffusive Behaviors of Deuterium in Nickel under Irradiation of Helium-3, Journal of Nuclear Science and Technology 29 (10) (1992) 947–956.doi:10.1080/18811248.1992.9731618

    work page doi:10.1080/18811248.1992.9731618 1992

  62. [64]

    Holzner, Determining fundamental transport parameters of hydrogen isotopes in tungsten, Ph.D

    G. Holzner, Determining fundamental transport parameters of hydrogen isotopes in tungsten, Ph.D. thesis, Report IPP 2020-09 (2020). URLhttp://hdl.handle.net/21.11116/0000-0007-4806-2

    2020

  63. [65]

    Frauenfelder, Solution and diffusion of hydrogen in tungsten, Journal of Vacuum Science and Technology 6 (3) (1969) 388–397.doi:10.1116/ 1.1492699

    R. Frauenfelder, Solution and diffusion of hydrogen in tungsten, Journal of Vacuum Science and Technology 6 (3) (1969) 388–397.doi:10.1116/ 1.1492699

    1969

  64. [66]

    Alnot, A

    P. Alnot, A. Cassuto, D. King, Adsorption and desorption kinetics with no precursor trapping: Hydrogen and deuterium on W 100, Surface Science 215 (1) (1989) 29–46.doi:10.1016/0039-6028(89)90697-3

    work page doi:10.1016/0039-6028(89)90697-3 1989

  65. [67]

    Ajmalghan, Z

    M. Ajmalghan, Z. Piazza, E. Hodille, Y. Ferro, Surface coverage depen- dent mechanisms for the absorption and desorption of hydrogen from 32 the W(110) and W(100) surfaces: a density functional theory investiga- tion, Nuclear Fusion 59 (10) (2019) 106022.doi:10.1088/1741-4326/ ab33e7

    work page doi:10.1088/1741-4326/ 2019

  66. [68]

    Ferro, E

    Y. Ferro, E. Hodille, J. Denis, Z. Piazza, M. Ajmalghan, Hydrogen and oxygen on tungsten (110) surface: adsorption, absorption and desorption investigated by density functional theory, Nuclear Fusion 63 (3) (2023) 036017.doi:10.1088/1741-4326/acb0e2

    work page doi:10.1088/1741-4326/acb0e2 2023

  67. [69]

    Hodille, B

    E. Hodille, B. Pavec, J. Denis, A. Dunand, Y. Ferro, M. Minissale, T. Angot, C. Grisolia, R. Bisson, Deuterium uptake, desorption and sputtering from w(110) surface covered with oxygen, Nuclear Fusion 64 (4) (2024) 046022.doi:10.1088/1741-4326/ad2a29

    work page doi:10.1088/1741-4326/ad2a29 2024

  68. [70]

    P. W. Tamm, L. D. Schmidt, Binding states of hydrogen on tungsten, The Journal of Chemical Physics 54 (1971) 4775–4787.doi:10.1063/ 1.1674753

    1971

  69. [71]

    Nicolás, The bar derived category of a curved dg algebra, Journal of Pure and Applied Algebra 212 (2008) 2633–2659

    M. Zibrov, S. Ryabtsev, Y. Gasparyan, A. Pisarev, Experimental deter- mination of the deuterium binding energy with vacancies in tungsten, Journal of Nuclear Materials 477 (2016) 292 – 297.doi:10.1016/j. jnucmat.2016.04.052

    work page doi:10.1016/j 2016

  70. [72]

    Hagelstein, Equation of state and fugacity models forH 2 and forD 2, Journal of Condensed Matter Nuclear Science 16 (2015) 23–45

    P. Hagelstein, Equation of state and fugacity models forH 2 and forD 2, Journal of Condensed Matter Nuclear Science 16 (2015) 23–45. URLhdl.handle.net/1721.1/122604

    2015

  71. [73]

    Gregoryanz, C

    E. Gregoryanz, C. Ji, P. Dalladay-Simpson, B. Li, R. T. Howie, H.-K. Mao, Everything you always wanted to know about metallic hydrogen but were afraid to ask, Matter and Radiation at Extremes 5 (3) (2020) 038101.doi:10.1063/5.0002104

    work page doi:10.1063/5.0002104 2020

  72. [74]

    Diatschenko, C

    V. Diatschenko, C. W. Chu, D. H. Liebenberg, D. A. Young, M. Ross, R. L. Mills, Melting curves of molecular hydrogen and molecular deu- terium under high pressures between 20 and 373 K, Phys. Rev. B 32 (1985) 381–389.doi:10.1103/PhysRevB.32.381

    work page doi:10.1103/physrevb.32.381 1985

  73. [75]

    J.-M. Joubert, A calphad-type equation of state for hydrogen gas and its application to the assessment of Rh–H system, International Journal of Hydrogen Energy 35 (2010) 2104–2111.doi:10.1016/j.ijhydene. 2010.01.006. 33

    work page doi:10.1016/j.ijhydene 2010

  74. [76]

    Joubert, S

    J.-M. Joubert, S. Thi´ ebaut, A thermodynamic description of the system Pd–Rh–H–D–T, Acta Materialia 59 (2011) 1680–1691.doi:10.1016/ j.actamat.2010.11.035

    2011

  75. [77]

    Kolasinski, D

    R. Kolasinski, D. Cowgill, R. Causey, A continuum-scale model of hy- drogen precipitate growth in tungsten plasma-facing materials, Journal of Nuclear Materials 415 (2011) S676–S679.doi:10.1016/j.jnucmat. 2010.10.077

    work page doi:10.1016/j.jnucmat 2011

  76. [78]

    Schwarz-Selinger, J

    T. Schwarz-Selinger, J. Bauer, S. Elgeti, S. Markelj, Influence of the presence of deuterium on displacement damage in tungsten, Nuclear Materials and Energy 17 (2018) 228–234.doi:10.1016/j.nme.2018. 10.005

    work page doi:10.1016/j.nme.2018 2018

  77. [79]

    San Marchi, B

    C. San Marchi, B. Somerday, S. Robinson, Permeability, solubility and diffusivity of hydrogen isotopes in stainless steels at high gas pressures, International Journal of Hydrogen Energy 32 (2007) 100–116.doi: 10.1016/j.ijhydene.2006.05.008. 34

    work page doi:10.1016/j.ijhydene.2006.05.008 2007