journal article·2022-12

Deuterium permeability of Russian fusion structural materials

D.I. Cherkez, A.V. Golubeva, A.V. Spitsyn, V.M. Chernov

Publisher page

Abstract

Nowadays, three classes of materials are considered the most relevant as the structural materials for fusion facilities: the austenitic steels, reduced activation ferritic-martensitic steels (RAFMS) and V-Cr-Ti alloys. In Russian Federation, the materials of all three types are developed and industrially produced: the ChS-68 austenitic steel, the Ek-181 RAFMS, and the V-4Cr-4Ti alloy. In this work, the deuterium permeability was studied of the fusion-relevant structural materials produced in Russia. Gas-driven permeation measurements were performed in a pressure range of 0.1÷5⋅10 4 Pa and in a temperature range of 290÷600 °C. Deuterium diffusion and permeation coefficients for the ChS-68 steel were found out. Permeability of the V-4Cr-4Ti alloy was estimated. At the same membrane temperature and D 2 pressure at the inlet surface, the deuterium flux permeating through the oxidized Ek-181 RAFMS is the lowest, the flux through the ChS-68 austenitic steel is several times higher, and the flux through vanadium alloy is 3–4.5 orders of magnitude higher.
Source: expertdata · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Magnetic confinement fusion research

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (33)

Show source-provided references
1. Belovodskiy · 1985
2. Long-term evaluation of the biological half-life of tritium
3. Tritium resources available for fusion reactors
4. Prospect of development and manufacturing of low activation metallic materials for fusion reactor10.1016/S0022-3115(96)00281-4 ↗
5. Nuclear physical properties of ferritic-martensitic steel EK-181 under conditions of long-term neutron irradiation in fast breeder BN-600 and fusion DEMO-RF reactors10.1134/S2075113311020067 ↗
6. Structural materials for fusion power reactors—The RF R&D activities10.1088/0029-5515/47/8/015 ↗
7. «High-dose neutron irradiation embrittlement of RAFM steels»10.1016/j.jnucmat.2006.04.014 ↗
8. Physical properties of F82H for fusion blanket design10.1016/j.fusengdes.2013.12.005 ↗
9. Shen · 2021 · 549 · 6
10. Study of reactor irradiation impact on deuterium permeation through stainless steel SS316IG
11. Production of ingots and flat-rolled products from low-activation high-purity vanadium alloys
12. A facility for permeation measurements under plasma irradiation10.1134/S0020441217050190 ↗
13. Nuclear physical properties of V-4Ti-4Cr alloy under prolonged neutron irradiation in bn-600 fast and DEMO-RF fusion reactors
14. A.V. Golubeva, R.P. Khvostov, D.I. Cherkez, N.P. Bobyr et al., GDP stand for the study of hydrogen permeability of membranes at interaction with gas, Instruments & experimental techniques,2022, in press10.1134/S0020441222050050 ↗
15. «Gas-driven hydrogen permeation in the surface-limited regime»10.1016/S0022-3115(03)00110-7 ↗
16. A.V. Golubeva, N.P. Bobyr, D.I. Cherkez, A.V. Spitsyn et al., Hydrogen interaction with the low activation ferritic–martensitic steel EK-181 (Rusfer), 2013, pp. S983–S98710.1016/j.jnucmat.2013.01.214 ↗
17. Deuterium permeation through Eurofer and α-alumina coated Eurofer10.1016/j.jnucmat.2004.03.008 ↗
18. Interaction of hydrogen isotopes with ferritic-martensitic steel ek-181-rusfer (review of results obtained)
19. «Properties of chromia scales on high-temperature alloys used as barriers against hydrogen permeation»10.1016/0022-3115(90)90351-M ↗
20. Surface effects in diffusion measurements deuterium permeation through martensitic steel10.1238/Physica.Topical.094a00121 ↗
21. Control of substrate oxidation in MOD ceramic coating on low-activation ferritic steel with reduced-pressure atmosphere
22. Effects of oxidation on the deuterium permeation behavior of the SIMP steel10.1016/j.ijhydene.2019.05.046 ↗
23. Hydrogen permeation behaviour in austenitic stainless steels10.1016/0921-5093(89)90857-5 ↗
24. Deuterium transport and isotope effects in type 316L stainless steel at high temperatures for nuclear fusion and nuclear hydrogen technology applications10.1016/j.cap.2014.08.006 ↗
25. Study of reactor irradiation impact on deuterium permeation through stainless steel SS316IG
26. Deuterium Permeation Through Reduced Activation V-4Cr-4Ti Alloy and V-4Cr-4Ti Alloy with AlN/Al Coatings10.1134/S1063778819070056 ↗
27. Gordienko · 2014 · 324
28. “Hydrogen permeation through vanadium alloy V–4Cr–4Ti ‘in situ’ of reactor irradiation”10.1016/S0022-3115(00)00148-3 ↗
29. Hydrogen permeation through Vanadium and the effect of surface impurity layer on it10.1016/0022-3115(82)90389-0 ↗
30. Concept of the divertor of a fusion neutron source based on a spherical Tokamak”10.1134/S1063780X12060116 ↗
31. Three-dimensional model of DEMO-FNS facility considering neutronics andradiation shield problems10.1016/j.heliyon.2019.e01630 ↗
32. «Tritium transport analysis in HCPB DEMO blanket with the FUS-TPC code»10.1016/j.fusengdes.2013.05.045 ↗
33. «Tritium diffusive transport parameters and trapping effects in the reduced activating martensitic steel OPTIFER-IVb»10.1016/S0022-3115(00)00188-4 ↗