Tritium and helium embrittlement of austenitic steels used in tritium storage and delivery system
Source abstract
Abstract
Abstract Embrittlement caused by tritium and helium produced as the beta-decay product of tritium affects the structural integrity of materials used in nuclear fusion reactors. We assess the embrittlement of 316L stainless steel used as the primary vessel in the tritium storage and delivery system with a planned operation scenario for the International Thermonuclear Experimental Reactor. First, based on the current system design and planned operation scenario, the tritium and helium concentrations in the primary vessel material are calculated. The effects of tritium and helium on the mechanical properties are estimated in comparison with available experimental data. We conclude that, if a forged material is used, the mechanical properties of the primary vessel will not significantly degrade over planned operation in terms of fracture toughness. In addition, fatigue and creep are expected not to be significant. Last, we discuss two possible methods to lower the concentration of helium for the purpose of reducing the residual risk.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Superconducting Materials and Applications
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (75)
Show source-provided references
1. Development of depleted uranium bed for tritium fuel cycle and basic absorption/desorption experiments10.1016/j.fusengdes.2018.04.123 ↗
2. Kolasinski · 2010
3. Fracture toughness of type 304 and 316 stainless steels and their welds10.1179/imr.1997.42.2.45 ↗
4. Micro-mechanical investigation for effects of helium on grain boundary fracture of austenitic stainless steel10.1016/j.jnucmat.2014.11.062 ↗
5. Caskey · 1983
6. Tritium-helium effects in metals10.13182/FST85-A24622 ↗
7. Kramer · 1968
8. Effects of internal helium on tensile properties of austenitic stainless steels and related alloys at 820°C
9. Helium embrittlement in type 304 stainless steel10.1016/0022-3115(68)90038-X ↗
10. Hydrogen interaction with stainless steel 12Cr18Ni10Ti containing radiogenic 3 He10.13182/FST11-A12730 ↗
11. The influence of helium on the high temperature mechanical properties of an austenitic stainless steel10.1016/0022-3115(78)90450-6 ↗
12. Tritium and decay helium effects on the fracture toughness properties of types 316L, 304L and 21Cr-6Ni-9Mn stainless steels
13. Thermal fatigue and creep evaluation for the bed in tritium SDS10.1016/j.fusengdes.2016.02.013 ↗
14. Mannone · 2012 · 90
15. The determination of the displacement energy in type 316 austenitic steel10.1016/0022-3115(77)90235-5 ↗
16. Datz · 1975 · 105
17. Defect production in ceramics10.1016/S0022-3115(97)00224-9 ↗
18. Optimal design of the multi-bed storage system in fusion fuel cycle under periodic demand based on the state-task network representation10.1016/j.ijhydene.2016.07.078 ↗
19. ITER Organization
20. Helium release from various metals10.1116/1.568578 ↗
21. Effect of boundary conditions on the kinetics of helium release from structural materials10.1134/S0031918X15090185 ↗
22. Low-temperature release of ion-implanted helium from nickel10.1063/1.93253 ↗
23. Low-temperature helium release in nickel10.1063/1.325848 ↗
24. Thermal stability of helium-vacancy clusters and bubble formation - multiscale modeling approach for fusion materials development10.13182/FST03-A374 ↗
25. The effects of grain boundary structure on binding of He in Fe10.1016/j.jnucmat.2004.04.262 ↗
26. Trapping of hydrogen and helium at grain boundaries in nickel: an atomistic study10.1007/BF02663018 ↗
27. Thermodynamic model for grain boundary effects on hydrogen solubility, diffusivity and permeability in poly-crystalline tungsten10.1016/j.fusengdes.2016.08.001 ↗
28. Molecular dynamics simulation on stability and diffusivity of hydrogen around a <111> symmetric tilt grain boundary in bcc-Fe10.1016/j.fusengdes.2018.04.092 ↗
29. Hydrogen permeation behaviour in austenitic stainless steels10.1016/0921-5093(89)90857-5 ↗
30. Deuterium transport through 304 and 304L stainless steel at low driving pressures and 15 KeV deuteron bombardment10.1016/0022-3115(78)90435-X ↗
31. Hydrogen and deuterium transport through type 304 stainless steel at elevated temperatures10.1080/18811248.1981.9733235 ↗
32. Nelson · 1973
33. Permeability, solubility and diffusivity of hydrogen isotopes in stainless steels at high gas pressures10.1016/j.ijhydene.2006.05.008 ↗
34. Hydrogen in 316 steel — diffusion, permeation and surface reaction10.1016/0022-3115(88)90319-4 ↗
35. The behavior of diffusion and permeation of tritium through 316L stainless steel10.1016/0022-3115(91)90091-K ↗
36. 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 ↗
37. Hydrogen uptake in austenitic stainless steels by exposure to gaseous hydrogen and its effect on tensile deformation10.1016/j.corsci.2011.04.022 ↗
38. The heats of formation of uranium hydride, uranium deuteride and uranium tritide at 25° 110.1021/ja01611a013 ↗
39. 2015 · 29
40. ITER hydrogen isotope separation system conceptual design description10.1016/0920-3796(90)90035-5 ↗
41. Simulation of hydrogen isotope separation by cryogenic distillation10.13182/FST92-A29874 ↗
42. Morgan
43. M.J. Morgan, N.T. Switzner, C. San Marchi, D.K. Balch, Forging strain rate and deformation temperature effects on the fracture toughness properties of type 304L stainless steel precharged with tritium, in: Int. Hydrog. Conf. (IHC 2016) Mater. Perform. Hydrog. Environ., ASME Press, n.d.: pp. 1–8. https://doi.org/10.1115/1.861387_ch18.10.1115/1.861387_ch18 ↗
44. Switzner
45. Effect of forging strain rate and deformation temperature on the mechanical properties of warm-worked 304L stainless steel10.1016/j.jmatprotec.2010.01.014 ↗
46. Tosten
47. Tritium barriers and tritium diffusion in fusion reactors10.1016/B978-0-08-056033-5.00116-6 ↗
48. Helium damage in austenitic stainless steels
49. Hydrogen embrittlement of metals10.1016/0025-5416(72)90109-7 ↗
50. Microstructural aspects of he embrittlement in type 316 stainless steel10.1016/0022-3115(82)90699-7 ↗
51. Evaluation of helium embrittlement by two dimensional elastic—plastic finite element method10.1016/S0022-3115(96)00270-X ↗
52. The theory of void nucleation in metals10.1016/0001-6160(78)90071-8 ↗
53. A three-dimensional meso-scale computer modeling for bubble growth in metals10.1088/0965-0393/16/5/055003 ↗
54. Internal reversible hydrogen embrittlement of austenitic stainless steels based on type 316 at low temperatures10.2355/isijinternational.52.240 ↗
55. Hydrogen effects in austenitic stainless steels10.1016/0921-5093(90)90348-7 ↗
56. Hydrogen effects on fracture toughness of type 316L stainless steel from 175 K to 425 K
57. The roles of internal and external hydrogen in the deformation and fracture processes at the fatigue crack tip zone of metastable austenitic stainless steels10.1016/j.scriptamat.2018.08.003 ↗
58. 2016
59. Mechanical behavior of face-centered cubic metals containing helium10.1016/0025-5416(75)90196-2 ↗
60. Tritium and helium effects on plastic deformation in AISI 316 stainless steel10.1016/0025-5416(87)90535-0 ↗
61. Tensile behavior of hydrogen-charged 316L stainless steel at elevated temperatures10.1016/j.msea.2013.12.011 ↗
62. Modeling of the tritium impact on mechanical properties of structural materials by radiogenic helium and hydrogen synergetic effect technique10.13182/FST05-A999 ↗
63. Hunn
64. Synergistic effects in hydrogen–helium bubbles10.1088/0953-8984/24/26/265402 ↗
65. Hydrogen effects in stainless steels
66. Hydrogen effects on the fracture toughness properties of forged stainless steels
67. Effect of tritium and decay helium on the fracture toughness properties of stainless steel weldments10.13182/FST08-A1863 ↗
68. Marchi · 2012
69. Effect of hydrogen on fatigue crack growth of metals10.1016/j.engfracmech.2010.04.012 ↗
70. Hydrogen embrittlement properties of stainless and low alloy steels in high pressure gaseous hydrogen environment10.2355/isijinternational.52.234 ↗
71. Fatigue life of helium-implanted AISI 316 L at 500 and 600°C10.1016/0022-3115(88)90450-3 ↗
72. Influence of light ion irradiation on fatigue crack propagation in austenitic stainless steel10.1016/0022-3115(88)90449-7 ↗
73. Creep properties and microstructures of helium implanted AISI 316L electron-beam weld and parent material10.1016/0920-3796(94)00410-9 ↗
74. 1990
75. Creep–fatigue endurance of 304 stainless steels10.1016/j.tafmec.2014.05.001 ↗