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Boron doping, combined with neutron capture in fission reactors, has been used to simulate the helium effect on fusion structural materials. However, inhomogeneous helium bubble formation was often observed due to boron segregation to grain boundaries. The excess radiation displacements due to 10B(n, α)7Li reaction, the high-energy lithium and helium ions, also were not accounted for, which can significantly accelerate the displacements-per-atom (dpa) accumulation alongside helium production (appm). Hereby an isotopically pure 10B doping approach is proposed to simulate the extreme environment inside fusion reactors with a high He appm-to-dpa ratio of about 10, which is about 102 × larger than in fission reactors. Computational modeling showed that ~13% of total radiation displacement was induced by 10B(n, α)7 Li in the case of 1 000 appm 10B doped Fe samples, which becomes even greater with increasing 10B loading. Spatially homogenous radiation damage and helium generation are predicted for grain sizes less than 1 μm, even if the boron partially formed precipitates or segregates on grain boundaries. Feasibility studies with various 10B doping (and 235U-codoping) levels in research reactors showed the estimated helium generation and radiation damage would significantly mimic fusion conditions and greatly expedite fusion materials testing, from many years down to months.
Kuang AQ, Cao NM, Creely AJ, Dennett CA, Hecla J, LaBombard B, et al. Conceptual design study for heat exhaust management in the ARC fusion pilot plant. Fusion Eng Des 2018;137:221–42. https://doi.org/10.1016/j.fusengdes.2018.09.007.
Mansur LK, Grossbeck ML. Mechanical property changes induced in structural alloys by neutron irradiations with different helium to displacement ratios. J Nucl Mater 1988;155–157:130–7. https://doi.org/10.1016/0022-3115(88)90235-8.
Schroeder H, Ullmaier H. Helium and hydrogen effects on the embrittlement of iron-and nickel-based alloys. J Nucl Mater 1991;179–181:118–24. https://doi.org/10.1016/0022-3115(91)90025-3.
Gilbert MR, Dudarev SL, Zheng S, Packer LW, Sublet JC. An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation. Nucl Fusion 2012;52. https://doi.org/10.1088/0029-5515/52/8/083019.
Molvik A, Ivanov A, Kulcinski GL, Ryutov D, Santarius J, Simonen T, et al. A gas dynamic trap neutron source for fusion material and subcomponent testing. Fusion Sci Technol 2010;57:369–94. https://doi.org/10.13182/FST10.
Sawan ME. Damage parameters of structural materials in fusion environment compared to fission reactor irradiation. Fusion Eng Des 2012;87:551–5. https://doi.org/10.1016/j.fusengdes.2012.01.022.
Xu HW, Kim SY, Chen D, Monchoux J-P, Voisin T, Sun C, et al. Materials genomics search for possible helium-absorbing nano-phases in fusion structural materials. Adv Sci 2022;9:2203555. https://doi.org/10.1002/advs.202203555.
Huang J, Liu H, Gao Z, Su Y, Liu Q, Ge W, et al. Helium-Hydrogen synergistic effects in structural materials under fusion neutron irradiation. Front Mater 2022;9. https://doi.org/10.3389/fmats.2022.849115.
Bhattacharya A, Meslin E, Henry J, Leprêtre F, Décamps B, Barbu A. Combined effect of injected interstitials and He implantation, and cavities inside dislocation loops in high purity Fe-Cr alloys. J Nucl Mater 2019;519:30-44. https://doi.org/10.1016/j.jnucmat.2019.03.043.
Zinkle SJ, Möslang A. Evaluation of irradiation facility options for fusion materials research and development. Fusion Eng Des 2013;88:472–82. https://doi.org/10.1016/j.fusengdes.2013.02.081.
Lisowski PW, Bowman CD, Russell GJ, Wender SA. Los alamos national laboratory spallation neutron sources. Nucl Sci Eng 1990;106:208–18. https://doi.org/10.13182/NSE90-A27471.
Schneider H-C, Dafferner B, Aktaa J. Embrittlement behaviour of different international low activation alloys after neutron irradiation. J Nucl Mater 2001;295:16-20. https://doi.org/10.1016/S0022-3115(01)00508-6.
Shiba K, Hishinuma A. Low-temperature irradiation effects on tensile and Charpy properties of low-activation ferritic steels. J Nucl Mater 2000;283–287:474–7. https://doi.org/10.1016/S0022-3115(00)00369-X.
Rieth M, Dafferner B, Röhrig HD. Embrittlement behaviour of different international low activation alloys after neutron irradiation. J Nucl Mater 1998;258–263:1147–52. https://doi.org/10.1016/S0022-3115(98)00171-8.
Okita T, Wolfer WG, Garner FA, Sekimura N. Influence of boron on void swelling in model austenitic steels. J Nucl Mater 2004;329–333:1013–6. https://doi.org/10.1016/j.jnucmat.2004.04.126.
Wakai E, Hashimoto N, Miwa Y, Robertson JP, Klueh RL, Shiba K, et al. Effect of helium production on swelling of F82H irradiated in HFIR. J Nucl Mater 2000;283–287:799-805. https://doi.org/10.1016/S0022-3115(00)00268-3.
Miwa Y, Wakai E, Shiba K, Hashimoto N, Robertson JP, Rowcliffe AF, et al. Swelling of F82H irradiated at 673 K up to 51 dpa in HFIR. J Nucl Mater 2000;283–287:334–48. https://doi.org/10.1016/S0022-3115(00)00222-1.
Klimenkov M, Möslang A, Materna-Morris E, Schneider H-C. Helium bubble morphology of boron alloyed EUROFER97 after neutron irradiation. J Nucl Mater 2013;442: S52 S57. https://doi.org/10.1016/j.jnucmat.2013.04.022.
Best SE, Fadaai A, Harling OK. Initial results using splat cooling in the development of boron doping for the simulation of fusion reactor helium embrittlement. J Nucl Mater 1979;85–86:835–8. https://doi.org/10.1016/0022-3115(79)90363-5.
Vitek JM, Klueh RL. Microstructure of 9 Cr-1 MoVNb steel irradiated to 36 dpa at elevated temperatures in HFIR. J Nucl Mater 1984;122:254–9. https://doi.org/10.1016/0022-3115(84)90606-8.
Maziasz PJ, Klueh RL, Vitek JM. Helium effects on void formation in 9Cr-1MoVNb and 12Cr-1MoVW irradiated in HFIR. Nucl Mater 1986;141–143:929–37. https://doi.org/10.1016/0022-3115(86)90120-0.
Klueh RL, Maziasz PJ, Vitek JM. Postirradiation tensile behavior of nickel-doped ferritic steels. J Nucl Mater 1984;141–143:960–5. https://doi.org/10.1016/0022-3115(86)90125-X.
Gelles DS, Garner FA. An experimental method to determine the role of helium in neutron-induced microstructural evolution. J Nucl Mater 1979;85–86:689–93. https://doi.org/10.1016/0022-3115(79)90340-4.
Materna-Morris E, Klimenkov M, Möslang A. The influence of boron on structural properties of martensitic 8-10%Cr-steels. Mater Sci Forum 2012;730–732:877-982. https://doi.org/10.4028/www.scientific.net/MSF.730-732.877.
Ziegler JF, Ziegler MD, Biersack JP. SRIM - the stopping and range of ions in matter. Nucl Instrum Methods Phys Res B 2010;268:1818-23. https://doi.org/10.1016/j.nimb.2010.02.091. 2010.
Stoller RE, Toloczko MB, Was GS, Certain AG, Dwaraknath S, Garner FA. On the use of SRIM for computing radiation damage exposure. Nucl Instrum Methods Phys Res B 2013;310:75-80. https://doi.org/10.1016/j.nimb.2013.05.008.
Agarwal S, Lin Y, Li C, Stoller RE, Zinkle SJ. On the use of SRIM for calculating vacancy production: quick calculation and full-cascade options. Nucl Instrum Methods Phys Res B 2021;503:11-29. https://doi.org/10.1016/j.nimb.2021.06.018.
Ren C, Yang Y, Li Y, Zhu Z, Li J. Sample spinning to mitigate polarization artifact and interstitial-vacancy imbalance in ion-beam irradiation. npj Comput Mater 2020;6:189. https://doi.org/10.1038/s41524-020-00438-9.
Duschanek H, Rogl P. Critical assessment and thermodynamic calculation of the binary system boron-tungsten (B-W). J Phase Equilibria Diffus 1995;16:150–61. https://doi.org/10.1007/BF02664852.
Zhang J, Liu J, Liao H, Zeng M, Ma S. A review on relationship between morphology of boride of Fe-B alloys and the wear/corrosion resistant properties and mechanisms. J Mater Res Technol 2019;8:6308–20. https://doi.org/10.1016/j.jmrt.2019.09.004.
Zhang L, Demkowicz MJ. Radiation-induced mixing between metals of low solid solubility. Acta Mater 2014;76:135–50. https://doi.org/10.1016/j.actamat.2014.05.013.
Schuler T, Nastar M, Soisson F. Vacancy-induced dissolution of precipitates in out-of-equilibrium systems: a test case of FeX (X= C,N,O) alloys. Phys Rev B 2017;95. https://doi.org/10.1103/PhysRevB.95.014113.
Hashimoto N, Klueh RL, Shiba K. Pros and cons of nickel-and boron-doping to study helium effects in ferritic/martensitic steels. J Nucl Mater 2002;307–311:222–8. https://doi.org/10.1016/S0022-3115(02)01183-2.
Horton LL, Bentley J, Farrell K. A TEM study of neutron-irradiated iron. J Nucl Mater 1982;108–109:222–3. https://doi.org/10.1016/0022-3115(82)90490-1.
Hu X, Koyanagi T, Fukuda M, Kiran Kumar NAP, Snead LL, Wirth BD, et al. Irradiation hardening of pure tungsten exposed to neutron irradiation. J Nucl Mater 2016;480:235–43. https://doi.org/10.1016/j.jnucmat.2016.08.024.
Sawan ME. Damage parameters of structural materials in fusion environment compared to fission reactor irradiation. Fusion Eng Des 2012;87:551–5. https://doi.org/10.1016/j.fusengdes.2012.01.022.
Sawan ME. Damage parameters of structural materials in fusion environment compared to fission reactor irradiation. Fusion Eng Des 2012;87:551–5. https://doi.org/10.1016/j.fusengdes.2012.01.022.
Mansur LK, Farrell K. On mechanisms by which a soft neutron spectrum may induce accelerated embrittlement. J Nucl Mater 1990;170:236–45. https://doi.org/10.1016/0022-3115(90)90294-W.
Tian Y, Chadha K, Arans C. Laser powder bed fusion of ultra-high-strength 420 stainless steel: microstructure characterization, texture evolution and mechanical properties. Mater Sci Eng 2021;805:140790. https://doi.org/10.1016/j.msea.2021.140790.
Gao R, Jin M-M, Li Q-J, So KP, Zhang L-F, Wang X-P, Fang Q-F, Sun C, Shao L, Li J. “Hybrid diffusive-displacive helium outgassing in Cu/Nb multilayer composites,”. Scripta Materialia 2021;194:113706.
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