Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method and helium presence
Source abstract
Abstract
The retention of deuterium in tungsten-chromium-yttrium alloys, W-11.4Cr-0.6Y and W-10Cr-0.5Y, was investigated by means of in-situ thermal desorption spectroscopy (TDS). The first alloy was manufactured by field-assisted sintering technology (FAST), while W-10Cr-0.5Y alloy was produced by hot isostatic pressing followed by heat treatment (HIP+HT). Both alloys were irradiated with D 3 + ions (670 eV/D) and a fluence of 10 21 D/m 2 at temperatures of 300, 600, 900 K. In the case of W-11.4Cr-0.6Y alloy, deuterium retention was investigated during sequential irradiation with helium (3 keV) and deuterium (670 eV/D) ions at room temperature with fluences of 10 19 –7 × 10 22 He/m 2 and 10 21 D/m 2 , respectively. The material structure has a great influence on deuterium retention, as evidenced by the significantly increased deuterium trapping in W-11.4Cr-0.6Y alloy at both room and elevated irradiation temperatures due to the presence of high-energy trapping centers compared to W-10Cr-0.5Y alloy. In both alloys, the observed amount of deuterium released during TDS was higher than in pure tungsten . The general trend of helium influence on the deuterium retention in W-11.4Cr-0.6Y alloy is very similar to bare tungsten. Namely, deuterium retention increased until helium implantation reached a fluence of 10 21 He/m 2 , and then sharply decreased when the fluence exceeded this value.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Advanced materials and composites
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (47)
Show source-provided references
1. Tokamak devices10.1088/0029-5515/12/2/012 ↗
2. In-vessel dust and tritium control strategy in ITER10.1016/j.jnucmat.2013.01.217 ↗
3. B. Lipschultz, J. Roth, J.W. Davis, R.P. Doerner, A.A. Haasz, A. Kallenbach, A. Kirschner, R.D. Kolasinski, A. Loarte, V. Philipps, K. Schmid, W.R. Wampler, G.M. Wright, D.G. Whyte1, An assessment of the current data affecting tritium retention and its use to project towards T retention in ITER, (2010) 1–60.
4. Effect of He on D retention in W exposed to low-energy, high-fluence (D, He, Ar) mixture plasmas10.1088/0029-5515/51/12/129501 ↗
5. Deuterium retention in tungsten exposed to low-energy pure and helium-seeded deuterium plasmas10.1063/1.3505754 ↗
6. Effect of helium irradiation on deuterium permeation behavior in tungsten10.1016/j.jnucmat.2017.04.041 ↗
7. Surface morphology and deuterium retention in tungsten exposed to low-energy, high flux pure and helium-seeded deuterium plasmas10.1088/0031-8949/2009/T138/014048 ↗
8. Overview of goals and performance of ITER and strategy for plasma-wall interaction investigation10.1016/j.jnucmat.2004.09.063 ↗
9. Physics basis for the first ITER tungsten divertor
10. Tungsten as a Plasma-Facing Material10.1016/B978-0-08-056033-5.00118-X ↗
11. Issues and strategies for DEMO in-vessel component integration10.1016/j.fusengdes.2016.05.040 ↗
12. E. Lassner, W.D. Schubert, Tungsten, 1999. doi:10.1007/978-1-4615-4907-9.10.1007/978-1-4615-4907-9 ↗
13. A review on two previous divertor target concepts for DEMO: mutual impact between structural design requirements and materials performance10.1088/0029-5515/55/11/113026 ↗
14. Overview of EU DEMO design and R&D activities10.1016/j.fusengdes.2014.01.070 ↗
15. On use of beryllium in fusion reactors: resources, impurities and necessity of detritiation after irradiation10.1016/j.fusengdes.2016.02.073 ↗
16. ITER monoblock performance under lifetime loading conditions in magnum-PSI10.1088/1402-4896/ab66df ↗
17. Experimental study of PFCs erosion and eroded material deposition under ITER-like transient loads at the plasma gun facility QSPA-T10.1016/j.jnucmat.2011.01.013 ↗
18. Cracks avoidance with a modified solid tungsten divertor in ASDEX Upgrade10.1016/j.fusengdes.2018.04.066 ↗
19. Development of yttrium-containing self-passivating tungsten alloys for future fusion power plants10.1016/j.nme.2016.07.011 ↗
20. New oxidation-resistant tungsten alloys for use in the nuclear fusion reactors10.1088/1402-4896/aa81f5 ↗
21. Advanced smart tungsten alloys for a future fusion power plant10.1088/1361-6587/aa6948 ↗
22. High temperature microstructural stability of self-passivating W-Cr-Y alloys for blanket first wall application10.1016/j.fusengdes.2019.02.136 ↗
23. Self-passivating tungsten alloys of the system W-Cr-Y for high temperature applications10.1016/j.ijrmhm.2018.01.018 ↗
24. WCrY smart alloys as advanced plasma-facing materials – Exposure to steady-state pure deuterium plasmas in PSI-210.1016/j.nme.2018.05.002 ↗
25. Deuterium retention in tungsten based materials for fusion applications10.1016/j.nme.2018.12.032 ↗
26. Analysis of trapping sites for deuterium in W–Cr–Y SMART alloy10.1016/j.vacuum.2022.110956 ↗
27. Smart first wall materials for intrinsic safety of a fusion power plant10.1016/j.fusengdes.2018.04.028 ↗
28. Oxidation resistance of bulk plasma-facing tungsten alloys10.1016/j.nme.2018.05.003 ↗
29. Deuterium trapping in the subsurface layer of tungsten pre-irradiated with helium ions10.1016/j.jnucmat.2021.152848 ↗
30. Influence of the Initial Defect Structure on Helium Trapping in Tungsten under Ion Implantation10.1134/S1063778818110170 ↗
31. Hydrogen in tungsten as plasma-facing material10.1088/0031-8949/2011/T145/014031 ↗
32. A setup for thermodesorption measurements10.1134/S0020441209060219 ↗
33. The Cr−W (Chromium−Tungsten) system10.1007/BF02868555 ↗
34. Helium retention in tungsten under plasma and ion beam irradiation and its impact on surface morphology10.1088/1402-4896/ab4068 ↗
35. Systematic investigation of the formation behavior of helium bubbles in tungsten10.1016/j.jnucmat.2014.10.098 ↗
36. Hydrogen exchange with voids in tungsten observed with TDS and PA10.1016/0022-3115(88)90478-3 ↗
37. Modelling deuterium release during thermal desorption of D+-irradiated tungsten10.1016/j.jnucmat.2007.09.028 ↗
38. Effect of nanostructure on radiation tolerance and deuterium retention in tungsten10.1063/1.4996096 ↗
39. Deuterium retention in dense and disordered nanostructured tungsten coatings10.1016/j.jnucmat.2018.04.039 ↗
40. Sublimation of advanced tungsten alloys under DEMO relevant accidental conditions10.1016/j.fusengdes.2019.02.039 ↗
41. Helium isotope exchange in tungsten irradiated sequentially with 4He and 3He ions10.1016/j.jnucmat.2022.154094 ↗
42. Deuterium retention in tungsten in dependence of the surface conditions10.1016/S0022-3115(02)01375-2 ↗
43. Pre-implantation and pre-annealing effects on deuterium retention in tungsten10.1016/j.jnucmat.2007.06.003 ↗
44. Microstructure evolution in tungsten during low-energy helium ion irradiation10.1016/S0022-3115(00)00289-0 ↗
45. Retention of deuterium in the surface layers of Tungsten preliminarily irradiated with helium ions10.3103/S1062873820060040 ↗
46. Simultaneous irradiation effects of hydrogen and helium ions on tungsten10.1016/j.jnucmat.2008.12.300 ↗
47. Deuterium and helium retention and corresponding modifications of W under heat loads relevant to ITER transient plasma events: part I. The power load below the tungsten melting temperature10.1016/j.jnucmat.2021.153328 ↗