The natural aging of austenitic stainless steels irradiated with fast neutrons
Source abstract
Abstract
Abstract Much of today's research in nuclear materials relies heavily on archived, historical specimens, as neutron irradiation facilities become ever more scarce. These materials are subject to many processes of stress- and irradiation-induced microstructural evolution, including those during and after irradiation. The latter of these, referring to specimens “naturally aged” in ambient laboratory conditions, receives far less attention. The long and slow set of rare defect migration and interaction events during natural aging can significantly change material properties over decadal timescales. This paper presents the results of natural aging carried out over 15 years on austenitic stainless steels from a BN-350 fast breeder reactor, each with its own irradiation, stress state, and natural aging history. Natural aging is shown to significantly reduce hardness in these steels by 10–25% and partially alleviate stress-induced hardening over this timescale, showing that materials evolve back towards equilibrium even at such a low temperature. The results in this study have significant implications to any nuclear materials research program which uses historical specimens from previous irradiations, challenging the commonly held assumption that materials “on the shelf” do not evolve.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Nuclear materials and radiation effects
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (50)
Show source-provided references
1. Site characterization of the Yucca Mountain disposal system for spent nuclear fuel and high-level radioactive waste10.1016/j.ress.2013.06.020 ↗
2. Reexamination of reactor pressure-vessels of the decommissioned greifswald nuclear-power-plant - opportunity for realistic evaluation of neutron embrittlement
3. Radiation-induced degradation of stainless steel light water reactor internals10.1016/j.mser.2012.05.002 ↗
4. Mechanical properties and microstructure of long term thermal aged WWER 440 RPV steel10.1016/j.jnucmat.2017.01.007 ↗
5. Development of the safety case for a spent fuel dry storage facility in Kazakhstan, a case study
6. Characterizing and packaging BN-350 spent fuel for long-term dry storage
7. Materials aging at the mesoscale: kinetics of thermal, stress, radiation activations
8. In-reactor deformation of cold-worked Zr-2.5Nb pressure tubes
9. Irradiation creep and void swelling of austenitic stainless steels at low displacement rates in light water energy systems10.1016/S0022-3115(97)00260-2 ↗
10. Embrittlement of RPV steels: an atom probe tomography perspective10.1016/j.jnucmat.2007.05.003 ↗
11. Recent developments in irradiation-resistant steels10.1146/annurev.matsci.38.060407.130315 ↗
12. Void-swelling in irons and ferritic steels, 2. Experimental survey of materials irradiated in a fast-reactor10.1016/0022-3115(79)90123-5 ↗
13. Potential high fluence response of pressure vessel internals constructed from austenitic stainless steels
14. Irradiation creep and void swelling of austenitic stainless steels at low displacement rates in light water energy systems10.1016/S0022-3115(97)00260-2 ↗
15. Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS10.1016/S0022-3115(03)00003-5 ↗
16. Baffle bolt failures - a B&W owners group approach10.1016/S0029-5493(99)00128-4 ↗
17. Influence of stresses on radiational swelling and vacancy porosity parameters of neutron irradiated austenite steels
18. Recent progress in understanding reactor pressure vessel steel embrittlement10.1080/10420159808229676 ↗
19. Effects of neutron irradiation on microstructures and hardness of stainless steel weld-overlay cladding of nuclear reactor pressure vessels10.1016/j.jnucmat.2014.01.004 ↗
20. Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels10.1016/S0022-3115(02)00719-5 ↗
21. Low temperature thermal aging of austenitic stainless steel welds: kinetics and effects on mechanical properties10.1016/j.msea.2011.11.055 ↗
22. Evaluation of the effects of thermal aging of austenitic stainless steel welds using small punch test10.1016/j.proeng.2015.12.253 ↗
23. Materials-technology investigations of fuel elements, irradiated in a reactor at the Obninsk nuclear power plant, after standing for 38 years in a depository10.1007/BF02673157 ↗
24. Precipitate phases in type 321 stainless steel after aging 17 years at ∼600°C10.1007/BF02644866 ↗
25. The effect of neutron irradiation and long-term storage on mechanical and energy characteristics of stainless steel
26. BN-350 reactor fuel condition after irradiation and storage in cooling pool
27. Cahalan · 2006 · 3
28. Inhomogeneity of microstructure, mechanical properties, magnetism, and corrosion observed in a 12Cr18Ni10Ti fuel assembly shroud irradiated in BN-350 to 59 dpa10.1016/j.jnucmat.2015.09.021 ↗
29. Peculiarities of plastic flow involving “deformation waves” observed during low-temperature tensile tests of highly irradiated 12Cr18Ni10Ti and 08Cr16Ni11Mo3 steels10.1016/j.jnucmat.2010.06.010 ↗
30. Void swelling of AISI 321 analog stainless steel irradiated at low dpa rates in the BN-350 reactor10.1016/j.jnucmat.2007.03.170 ↗
31. Correlation of yield stress and microhardness in 08Cr16Ni11Mo3 stainless steel irradiated to high dose in the BN-350 fast reactor10.1016/j.jnucmat.2006.09.005 ↗
32. The defect microstructure and element composition in denuded zones of stainless steels irradiated in BN-350 nuclear reactor10.1557/adv.2016.647 ↗
33. Degradation in mechanical properties of stainless steels C0.12Cr18Ni10Ti and C0.08Cr16Ni11Mo3 – materials for hexagonal ducts of spent fuel assemblies from the BN-350 fast neutron reactor
34. Deformation induced martensitic transformation in Cr–Ni stainless steel irradiated by neutrons10.1002/1521-396X(199709)163:1<R7::AID-PSSA99997>3.0.CO;2-T ↗
35. Dislocation densities and stored energy after cold rolling of Al-Mg alloys: investigations by resistivity and differential scanning calorimetry10.1016/S1359-6462(97)00118-8 ↗
36. Stored energy in nickel cold rolled to large strains, measured by calorimetry and evaluated from the microstructure10.1007/s11661-007-9421-1 ↗
37. Radiation annealing effects in energetic displacement cascades10.1103/PhysRevB.16.3860 ↗
38. V.N. Karaulov, A.Р. Blynski, S.V. Golovnin, I.K. Yakovlev, E.V. Chumakov, K.K. Kadyrzhanov, H.G. Kadyrov, Т.Е. Turkebaev, J.D.B. Lambert. BN-350 core and blanket fuel condition after irradiation and wet storage. International Workshop “Nuclear Power Technologies” (NPT-2000), IAEA Tech. Report No. INIS-KZ–068, Accessed at http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/31/065/31065450.pdf on 2017-05-27.
39. Martensitic transformations in neutron irradiated and helium implanted stainless steels
40. G-phase precipitation in austenitic stainless steel deformed by high pressure torsion10.1016/j.msea.2012.05.030 ↗
41. Microstructural defect evolution in neutron-irradiated 12Cr18Ni9Ti stainless steel during subsequent isochronous annealing10.1016/j.jnucmat.2013.03.086 ↗
42. Role of irradiated microstructure and microchemistry in irradiation-assisted stress corrosion cracking10.1080/02678370412331320224 ↗
43. Influence of cluster mobility on Cu precipitation in α-Fe: a cluster dynamics modeling10.1016/j.actamat.2010.02.014 ↗
44. Diffusion of chromium in nanocrystalline iron produced by means of surface mechanical attrition treatment10.1016/S1359-6454(03)00260-X ↗
45. High-energy collision cascades in tungsten: dislocation loops structure and clustering scaling laws10.1209/0295-5075/103/46003 ↗
46. Direct observation of size scaling and elastic interaction between nano-scale defects in collision cascades10.1209/0295-5075/110/36001 ↗
47. Quantitative TEM analysis of precipitation and grain boundary segregation in neutron irradiated EUROFER9710.1016/j.jnucmat.2014.07.078 ↗
48. Thermal aging phenomena in cast duplex stainless steels10.1007/s11837-015-1709-9 ↗
49. Aging effects on microstructural and mechanical properties of select refractory metal alloys for space-reactor applications10.1016/j.jnucmat.2007.03.025 ↗
50. Evolution of the radiation-induced defect structure in 316 type stainless steel after post-irradiation annealing10.1016/j.jnucmat.2014.04.024 ↗