Chase N. Taylor ^a,*, Masashi Shimada ^a, Yuji Nobuta ^b, Makoto I. Kobayashi ^c, Yasuhisa Oya ^d, Yuji Hatano ^e, Takaaki Koyanagi ^f

a Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID, 83415, USA
b Laboratory of Plasma Physics and Engineering, Hokkaido University, Kita-13, Nishi-8, Kita-ku, Sapporo 060-8628, Japan
c National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan
d Graduate School of Science, Shizuoka University, 836 Ohya, Suruga-ku, Shizuoka 422-8529, Japan
e Hydrogen Isotope Research Center, University of Toyama, Toyama 930-8555, Japan
f Materials Science and Technology Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6138, USA

Abstract
Tritium (T) retention characteristics in dust collected from the divertor in JET with ITER-like wall (JET-ILW) after the third campaign in 2015–2016 (ILW-3) have been examined in individual dust particles by combining radiography (tritium imaging plate technique) and electron probe micro-analysis. The results are summarized and compared with the data obtained after the first campaign in 2011–2012 (ILW-1). The dominant component in ILW-1 dust was carbon (C) originating from tungsten-coated carbon fibre composite (CFC) tiles in JET-ILW divertor and/or legacy of C dust after the JET operation with carbon wall. Around 85% of the total tritium retention in ILW-1 dust was attributed to the C dust. The retention in tungsten (W) and beryllium (Be) dominated particles was 100 times smaller than the highest T retention in carbon-based particles. After ILW-3 the main component contributing to the T retention was W. The number of small W particles with T increased, in comparison to ILW-1, most probably by the exfoliation and fragmentation of W coatings on CFC tiles though T retention in individual W particles was smaller than in C particles. The detection of only very few Be-dominated dust particles found after ILW-1 and ILW-3 could imply stable Be deposits on the divertor tiles.

https://doi.org/10.1016/j.nme.2022.101323
Accepted:Accepted 29 November 2022

Jing Wang^a,b, Yuji Hatano ^a, Takeshi Toyama ^c, Tatsuya Hinoki ^d, Kiyohiro Yabuuchi ^e, Yi-fan Zhang ^b,Bing Ma^b, Alexander V. Spitsyn ^f, Nikolay P. Bobyr ^f, Koji Inoue ^c, Yasuyoshi Nagai^c

a Hydrogen Isotope Research Center, Organization for Promotion of Research, University of Toyama, Toyama 930-8555, Japan
b School of Materials Science and Engineering, Hefei University of Technology, Hefei 230009, China
c Institute for Materials Research, Tohoku University, Oarai 311-1313, Japan
d Open Innovation Institute, Kyoto University, Kyoto 606-8501, Japan
e Institute of Advanced Energy, Kyoto University, Kyoto 611-0011, Japan
f NRC "Kurchatov Institute", Kurchatov sq. 1, Moscow 123182, Russia

Abstract
Irradiation responses of binary W alloys were investigated systematically from the perspective of the binding energy of an alloying element with a W self-interstitial atom (W-SIA). Plates of W, W-0.3 at.% Cr, W-5 at.% Re, W-2.5 at.% Mo and W-5 at.% Ta alloys were irradiated at 1073 K with 6.4 MeV Fe ions to 0.26 dpa at the damage peak, where the binding energy of alloying element with W-SIA is in order of Cr > Re > Mo > Ta. The formation of vacancy-type defects (vacancies and vacancy clusters) was studied by using positron lifetime measurement. The precipitation of alloying elements was studied by using atom probe tomography (APT) and the hardness changes in the irradiated volumes were measured by the nanoindentation technique. The formation of vacancy-type defects was strongly suppressed by the addition of Cr and Re, while Ta and Mo had no noticeable suppression effect. The APT measurements.

https://doi.org/10.1016/j.matdes.2023.111899
Accepted:31 March 2023

S. Lee^1,∗, Y. Hatano¹, S. Masuzaki², Y. Oya³, M. Tokitani², M. Yajima², T. Otsuka⁴, N. Ashikawa², Y. Torikai⁵, N. Asakura⁶, H. Nakamura⁶, H. Kurotaki⁶, T. Hayashi⁶, T. Nozawa⁶, A.M. Ito², J. Likonen⁷, A. Widdowson⁸, M. Rubel⁹ and JET Contributorsa

1 University of Toyama, Toyama 930-8555, Japan
2 National Institute for Fusion Science, Toki 509-5292, Japan
3 Shizuoka University, Shizuoka 422-8529, Japan
4 Kindai University, Higashiosaka 577-8502, Japan
5 Ibaraki University, Mito 310-8512, Japan
6 National Institutes for Quantum Science and Technology, Rokkasho 039-3212, Japan
7 VTT, Otakaari 3J, PO Box 1000, FIN-02044 VTT, Espoo, Finland
8 Culham Centre for Fusion Energy, United Kingdom Atomic Energy Authority, Culham Science Centre, Abingdon OX14 3DB, United Kingdom
9 KTH Royal Institute of Technology, 10044 Stockholm, Sweden

Abstract
Tritium retention in the castellated structure of beryllium limiters used in JET with the ITER-like wall (ILW) during the first (ILW1), third (ILW3) and all three (ILW1-3) campaigns were examined and evaluated. Tritium was deposited on the surfaces inside the castellation grooves together with deuterium, beryllium, oxygen, carbon and small amounts of metallic impurities such as nickel, copper and tungsten. The tritium content after the ILW1 campaign was greater than after the ILW3 campaign. This is attributed to the steadily decreasing amount of carbon impurities in JET from campaign to campaign. The majority of tritium was retained in shallow regions in the grooves, up to 2 mm from the entrance to the gap. It was comparable on all sides of the castellation, i.e. no difference has been detected between the toroidal and poloidal gaps. Secondly, the tritium retention in the gaps was similar on all specimens independent of their position in the tokamak, while the retention on the plasma-facing surfaces clearly depended on the tile position. The tritium deposition patterns in the castellation were also compared with the deuterium distribution determined in earlier studies.

https://doi.org/10.1088/1741-4326/ac47b4
Accepted for publication: 7 February 2023

Yasuhisa Oya ^a,*, Kyosuke Ashizawa ^a, Fei Sun ^b, Shiori Hirata ^a, Naoko Ashikawa ^c,Yoji Someya ^d, Yuji Hatano ^e, Robert Kolasinski ^f, Chase N. Taylor ^g, Masashi Shimada ^g

a Graduate School of Integrated Science and Technology, Shizuoka University, Shizuoka 422-8529, Japan
b School of Material Science and Engineering, Hefei University of Technology, Hefei, Anhui 230009, P.R. China
c The Graduate University for Advanced Studies, SOKENDAI, Toki, Gifu 509-5292, Japan
d National Institutes for Quantum and Radiological Science and Technology (QST), Rokkasho, Aomori 039-3212, Japan
e Hydrogen Isotope Research Center, University of Toyama, Gofuku, Toyama 930-8555, Japan
f Sandia National Laboratories, Livermore, CA 94550, United States of America
g Idaho National Laboratory, Idaho Falls, ID 83415, United States of America

https://doi.org/10.1016/j.fusengdes.2023.113722
Accepted: 2 April 2023

V.Kh. Alimov ^a,*, J. Roth a, K. Sugiyama ^a, M.J. Baldwin ^b, R.P. Doerner ^b, Y. Hatano ^c

a Max-Planck-Institut für Plasmaphysik, 85748 Garching, Germany
b Center for Energy Research, University of California at San Diego, La Jolla, CA 92093-0417, USA
c Hydrogen Isotope Research Center, Organization for Promotion of Research, University of Toyama, Toyama 930-8555, Japan

Abstract
energies of 90 and 140 eV at exposure temperatures between 360 and 773 K to deuterium ion fluences between 3.8 × 10²³ and 6.3 × 10²⁵ m ^-2. RBS analysis of these plasma-exposed samples showed that the uppermost surface layers were enriched with tungsten and tantalum. Deuterium depth profiles in the plasma-exposed samples were examined using the energy-scanning NRA technique allowing measurements of the deuterium depth profiles at depths of up to about 9 μm. With an increase in the exposure temperature from 360 to 773 K, the deuterium retention in the 1 μm thick sub-surface layer decreased almost monotonically from about 1 × 10¹⁹ D/m² to 5 × 1017 D/m². The deuterium concentration at a depth of 8 μm demonstrated a different temperature dependence - with an increase in the exposure temperature from 360 to 500 K, the deuterium concentration significantly decreased from about 4 × 10 ^-3 to (4 ± 3) × 10 ^-5 at.%. With a further increase in the temperature up to 773 K, the deuterium concentration at a depth of 8 μm became equal to or less than 5 × 10 ⁵ at.%.

https://doi.org/10.1016/j.nme.2023.101430
Accepted:6 April 2023

Mitsuhiro Inoue ^a, Ren Chung Peng ^a, Hibiki Sagami ^a, Yuta Kasai ^a, Tomoya Suga ^a,Toshiya Shibayanagi ^b, Takayuki Abe ^a

a Hydrogen Isotope Research Center, Organization for Promotion of Research, University of Toyama
b Faculty of Sustainable Design, University of Toyama

Abstract
Herein, TiO₂ nanotubes (TiO₂-NTs) were used as bulky supports for the preparation of highly active CO₂ methanation catalysts to maintain the stability of the reaction at high gas flow rates. The nanotube shapes of the prepared TiO₂-NTs remained unchanged at a calcination temperature of 300 ℃. The CO₂ methanation reaction on Ru-sputtered catalysts indicated that at high gas flow rates of 10% CO₂/Ar and H₂, some crack-like gaps were formed in the catalyst bed using raw anatase TiO₂ particle supports, whereas no gaps appeared in the case where TiO₂-NTs were used as the support, leading to a stable reaction. This result is attributed to the formation of a sparse catalyst bed owing to the bulky TiO₂-NT supports.

https://doi.org/10.1016/j.matlet.2023.134787
Accepted:17 June 2023

Jiaqi Zhang¹,Akifumi Iwamoto², Keisuke Shigemori¹, Masanori Hara³and Kohei Yamanoi¹

1 Institute of Laser Engineering, Osaka University, 2-6 Yamadaoka, Suita, Osaka 565-0871, Japan
2 National Institute for Fusion Science, 322-6 Oroshi, Toki, Gifu 509-5292, Japan
3 Faculty of Science, Academic Assembly, University of Toyama, 3190 Gofuku, Toyama 930-8555, Japan

Abstract
Deuterium (D)-Tritium (T) nuclear fusion reaction has potential as an energy source in the future. In both magnetic confinement and inertial confinement fusion reactors, solid D–T will generally be supplied as fusion fuel. The efficiency of the nuclear fusion reaction depends on the quality of solid D–T fuel, which is related to the composition, homogeneity, helium-3 (³He) content, and so on. However, there is no technique for in-situ examination of solid D–T fuel. In this study, we consider a simple and precise method for the characterization of solid hydrogen isotopologues at cryogenic temperature using refractive index measurement, and evaluate the distribution of hydrogen isotopologue composition and homogeneity. To evaluate without the effect of tritium decay, the homogeneity of the hydrogen (H₂)-deuterium (D₂) mixture is measured at first. By the in-situ refractive index measurement at cryogenic temperature, the homogeneity of solid H₂–D₂ mixture is roughly quantified. The phase diagram of the H₂–D₂ mixture shows a solid solution type. D₂-rich crystal first appears from the liquid phase as a primary crystal. The composition of D₂ in liquid phase ias homogeneous, whereas it reduces by obeying the liquidus line in the phase diagram with the crystallization. On the other hand, the composition of the H₂–D₂ mixture in solid phase is inhomogeneous because the mobility of H₂ and D₂ in solid phase was too slow to be homogeneous and solid. The compositions of H₂–D₂ mixture in liquid and solid phases could be evaluated by the in-situ refractive index measurement in time. Consequently, the refractive index measurement shows great potential as an inspection method of solid D–T fuel in fusion reactors.

https://doi.org/10.1088/1741-4326/acd015
Accepted:29 October 2022

S. Lee¹, Y. Hatano¹, S. Masuzaki², Y. Oya³, M. Tokitani², M. Yajima², T. Otsuka⁴, N. Ashikawa², Y. Torikai⁵, N. Asakura⁶, H. Nakamura⁶, H.Kurotaki⁶, T. Hayashi⁶, T. Nozawa⁶, A.M. Ito², J. Likonen⁷, A. Widdowson⁸, M. Rubel⁹

1 University of Toyama, Toyama 930-8555, Japan
2 National Institute for Fusion Science, Toki 509-5292, Japan
3 Shizuoka University, Shizuoka 422-8529, Japan
4 Kindai University, Higashiosaka 577-8502, Japan
5 Ibaraki University, Mito 310-8512, Japan
6 National Institutes for Quantum Science and Technology, Rokkasho 039-3212, Japan
7 VTT, Otakaari 3J, PO Box 1000, FIN-02044 VTT, Espoo, Finland
8 Culham Centre for Fusion Energy, United Kingdom Atomic Energy Authority, Culham Science Centre,Abingdon OX14 3DB, United Kingdom
9 KTH Royal Institute of Technology, 10044 Stockholm, Sweden

Abstract
Tritium retention in the castellated structure of beryllium limiters used in JET with the ITER-like wall (ILW) during the first (ILW1), third (ILW3) and all three (ILW1-3) campaigns were examined and evaluated. Tritium was deposited on the surfaces inside the castellation grooves together with deuterium, beryllium, oxygen, carbon and small amounts of metallic impurities such as nickel, copper and tungsten. The tritium content after the ILW1 campaign was greater than after the ILW3 campaign. This is attributed to the steadily decreasing amount of carbon impurities in JET from campaign to campaign. The majority of tritium was retained in shallow regions in the grooves, up to 2 mm from the entrance to the gap. It was comparable on all sides of the castellation, i.e. no difference has been detected between the toroidal and poloidal gaps. Secondly, the tritium retention in the gaps was similar on all specimens independent of their position in the tokamak, while the retention on the plasma-facing surfaces clearly depended on the tile position. The tritium deposition patterns in the castellation were also compared with the deuterium distribution determined in earlier studies.

Keywords:JET-ITER like wall, tritium retention, beryllium limiters, castellation, deposition in gaps
Accepted for publication: 7 February 2023

Masanori Hara ^a,*, Yuya Fujimoto ^a, Satoshi Akamaru ^a, Tsukasa Aso ^b, Marco R¨ollig ^c
a University of Toyama, Gofuku 3190, Toyama 930-8555, Japan
b National Institute of Technology, Toyama College, Ebie-neriya 1-2, Imizu, Toyama 933-0293, Japan
c Karlsruhe Institute of Technology, P.O. Box 3640, Karlsruhe 76021, Germany

Abstract
Beta-ray induced X-ray spectrometry (BIXS) is commonly used for qualitative measurement of tritium in solids. We considered that BIXS could also be used quantitatively to determine the depth of tritium in solids. To determine the change in the shape of the BIX spectrum with tritium depth, spectra in aluminum and iron were calculated using the Monte Carlo simulation code (Galet-BIXS). The spectral shape was determined by the relative fractions of the characteristic X-ray components and bremsstrahlung. It was changed with the tritium depth, even when the number of tritium decay events was held constant in the simulations. Specifically, the spectral shape gave information about the tritium depth. However, the accuracy of the estimated tritium depth depended not only on the elements that interact with the beta particles but also on the tritium depth. In some cases, the tritium depth could not be evaluated from the BIX spectra. For example, the spectral shape for aluminum in helium was kept up to 10 μm deep of the tritium depth. When the atmosphere was replaced from helium to argon, the spectral shape was changed with the tritium depth up to 10 μm. Nevertheless, our method allows quantitative analysis of tritium in solids based on the BIX spectrum in most cases. We believe that the Monte Carlo simulation of the BIX spectrum is crucial to the further development to determine the tritium depth in solids.

https://doi.org/10.1016/j.fusengdes.2023.114009
Accepted:15 September 2023

Satoshi Akamaru,¹, Naoki Godo,² and Sakie Koshimoto²
1 Hydrogen Isotope Research Center, Organizational for Promotion of Research, University of Toyama
2Faculty of Science, University of Toyama

Abstract
The magnetoresistance of three Pd–Co(1)/Cu/Pd–Co(3) trilayers with different Pd–Co(3) thicknesses were evaluated in a H₂–N₂ gas mixture. The resistance of Pd–Co/Cu/Pd–Co increased with increasing hydrogen concentration in the gas phase, which is similar to the behavior observed in the Pd metal. The peak structure was shown in the magnetoresistance under a nitrogen atmosphere and was associated with magnetic scattering at the interface between the Pd–Co and Cu layers. In the H₂–N₂ gas mixture, the peak position and width in the resistance profiles were independent of the hydrogen concentration for all the prepared trilayers, and the peak intensity decreased with increasing hydrogen concentration for the trilayer containing a 4.2 nm thick Pd–Co(3) layer. The decrease in intensity was due to the reduction in magnetization in the Pd–Co layer after hydrogen absorption. The change in the resistance ratio by hydrogen absorption in the trilayer was larger under a high external magnetic field of 170 mT than under a low magnetic field of 10 mT. These results confirmed that the multilayered structure of the Pd–Co/Cu enhances the resistance response to hydrogen under a high magnetic field.

doi: 10.1063/5.0161802
Accepted:25 August 2023

Takuya NAGASAKA, Makoto I. KOBAYASHI, Teruya TANAKA, Sadatsugu TAKAYAMA, Hiroyuki NOTO, Jingjie SHEN, Tatsuya HINOKI¹⁾, Kiyohiro YABUUCHI²⁾, Katsuaki TANABE³⁾, Ryuta KASADA⁴⁾, Sosuke KONDO⁴⁾, Shuhei NOGAMI⁵⁾, Hiroki KURITA⁶⁾, Naoyuki HASHIMOTO⁷⁾, Yuji YAMAUCHI⁷⁾, Yasuhisa OYA⁸⁾, Takumi CHIKADA⁸⁾, Yuji HATANO⁹⁾, Kazunari KATAYAMA¹⁰⁾, Makoto OYA¹⁰⁾, Naoko OONO¹¹⁾ and Yoshitaka MORI¹²⁾

National Institute for Fusion Science, National Institutes of Natural Sciences, Toki, Gifu 509-5292, Japan
1)Open Innovation Institute, Kyoto University, Uji, Kyoto 611-0011, Japan
2)Institute of Advanced Energy, Kyoto University, Uji, Kyoto 611-0011, Japan
3)Department of Chemical Engineering, Kyoto University, Kyoto 615-8510, Japan
4)Institute for Materials Research, Tohoku University, Sendai, Miyagi 980-8577, Japan
5)Graduate School of Engineering, Tohoku University, Sendai, Miyagi 980-8579, Japan
6)Graduate School of Environmental Studies, Tohoku University, Sendai, Miyagi 980-8579, Japan
7)Graduate School of Engineering, Hokkaido University, Sapporo, Hokkaido 060-8628, Japan 8)Graduate School of Integrated Science and Technology, Shizuoka University, Shizuoka 422-8529, Japan 9)Hydrogen Isotope Research Center, University of Toyama, Toyama 930-8555, Japan
10)Interdisciplinary Graduate School of Engineering Sciences, Kyushu University, Kasuga, Fukuoka 816-8580, Japan
11)College of Engineering Science, Yokohama National University, Yokohama, Kanagawa 240-8501, Japan
12)The Graduate School for the Creation of New Photonics Industries, Hamamatsu, Shizuoka 431-1202, Japan

Abstract
The purpose of the research unit UlCoMat (Ultrahigh-flux Concerting Materials) is creation of novel materials for advanced engineering systems, such as fusion and fission reactors, aerospace craft, rockets and chemical plants, based on understanding and control of the metastable phase and the self-organization induced in materials under extreme conditions. The UlCoMat will accelerate a paradigm shift from stable and resistant materials to metastable but adaptive ones. It focuses also on the science of life to seek long-life materials and a precise estimation of their existence for the development of robust engineering systems using the minimum materials compatible with economical and safety requirements.

DOI: 10.1585/pfr.18.2505085
Accepted:21 April 2023

K. Miki ^a,d,∗, Y. Utsuki ^a,d, M. Hara ^b, Y. Hatano ^b, N. Imai ^c, M. Inoue ^a,d, M. Itoh ^e, K. Kameya ^a,d, S. Kitayama ^a,d, Y. Maruta ^a,d, Y. Matsuda ^e, Y. Saito ^a,d, D. Sakai ^a,d, T. Uesaka ^d, H. Umetsu ^a, R. Urayama ^a,d, J. Wang ^b, K. Kamada ^f, Y. Shoji ^f, A. Yoshikawa ^f

a Department of Physics, Tohoku University, Sendai, Miyagi, 980-8578, Japan
b Hydrogen Isotope Research Center, University of Toyama, Toyama, 930-8555, Japan
c Center for Nuclear Study, the University of Tokyo, Hongo, Tokyo 113-0033, Japan
d Nishina Center for Accelerator-based Science, RIKEN, Wako, Saitama, 351-0198, Japan
e Cyclotron and Radioisotope Center, Tohoku University, Sendai, Miyagi, 980-8578, Japan
f Institute for Material Research, Tohoku University, Sendai, Miyagi, 980-8577, Japan

Abstract
Aiming at the spectroscopy of a trineutron system via the ³H(𝓉, ³He)3𝓃 reaction, we fabricated a self-supporting Ti-³H target with 3.5-mg/cm² thickness, which is approximately 90 times greater than those in previous studies. We first established a procedure of fabricating flat and crack-free Ti-²H foils. Thereafter, we constructed a compact Sieverts device accommodated in a tritium glove box environment at the Hydrogen Isotope Research Center, University of Toyama, and fabricated a Ti-³H target based on the established procedure. We successfully obtained a Ti-³H target with dimensions of 9.2 mm (W) × 12.0 mm (H) × 80 μm (D) and a total tritium amount of 1.58 TBq.

https://doi.org/10.1016/j.nima.2023.168583
Accepted:26 July 2023

Makoto I. KOBAYASHI^1,2), Yuji HATANO³⁾, Masanori HARA³⁾, Yasuhisa OYA⁴⁾, Yuji YAMAUCHI⁵⁾, Teppei OTSUKA⁶⁾ and Takuya NAGASAKA^1,2)

1)National Institute for Fusion Science, National Institutes of Natural Sciences, Gifu 509-5292, Japan
2)The Graduate University for Advanced Studies, SOKENDAI, Gifu 509-5292, Japan
3)Hydrogen Isotope Research Center, University of Toyama, Toyama 930-8555, Japan
4)Graduate School of Integrated Science and Technology, Shizuoka University, Shizuoka 422-8529, Japan
5)Graduate School of Engineering, Hokkaido University, Sapporo 060-8628, Japan
6)School of Science and Engineering, Kindai University, Osaka 577-8502, Japan

Abstract
This paper reviews the control and the application of ultrahigh hydrogen flux in materials for fusion reactors and future hydrogen societies. Ultrahigh hydrogen flux can be efficiently formed by the combination of hydrogen plasma exposure and the surface modification method, similar to super-permeation. The paper discusses the possibility of the fabrication of oversaturated hydrogen storage materials and the effective tritium removal from the components using the ultrahigh hydrogen flux.

DOI: 10.1585/pfr.18.2105073
Accepted:3 July 2023

Yasuhisa Oya ^a,*, Nao Inozume ^a, Yuzuka Hoshino ^a, Naoaki Yoshida ^b, Tatsuya Hinoki ^c,Kiyohiro Yabuuchi ^c, Yuji Hatano ^d, Qilai Zhou ^a,e, Fei Sun ^f, Robert Kolasinski ^g,Chase N. Taylor ^h, Masashi Shimada ^h

a Graduate School of Integrated Science and Technology, Shizuoka University, Shizuoka 422-8529, Japan
b Kyushu University, Fukuoka, Japan
c Kyoto University, Kyoto, Japan
d University of Toyama, Toyama, Japan
e Wuhan University of Technology, Wuhan, China
f Hefei University of Technology, Hefei, China
g Sandia National Laboratories, Livermore, CA, USA
h Idaho National Laboratory, Idaho Falls, ID, USA

Abstract
The deuterium (D) retention for 1 dpa Fe ion damaged W-10%Re with dynamic-annealing or post-annealing was investigated by TDS. Major D₂ desorption was observed at temperatures of 400, 650 and 850 K for 1 dpa damaged W-10%Re without annealing (room temperature). By dynamic-annealing above 573 K, the D₂ desorption stage at 850 K was clearly eliminated. On the other hand, it was found that post-annealing at a higher temperature of 1173 K was required to annihilate this desorption stage. This indicates that the D desorption from the irradiation defects introduced at room temperature (post-annealing) needs higher annealing temperature compared to the dynamic-annealing. The D retention for dynamic-annealed sample was reduced by the recovery of D trapping sites by annealing.

https://doi.org/10.1016/j.fusengdes.2023.113981
Accepted:29 August 2023