journal article·2025-05

Swelling behavior of Cr16Ni19 steel under neutron irradiation: experimental and theoretical analysis

Alexey Yanilkin, Alexander Kozlov, Irina Portnykh

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OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Ion-surface interactions and analysis

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References (25)

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1. Materials for future nuclear energy systems10.1016/j.jnucmat.2019.151837 ↗
2. Development of radiation porosity in austenitic EK164-ID c.d. Steel irradiated at 715–815 K to damage doses of 72–92 dpa10.1134/S0036029521030113 ↗
3. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure10.1016/S0022-3115(99)00225-1 ↗
4. Characteristics of radiation porosity and structural phase state of reactor austenitic 07C–16Cr–19Ni–2Mo–2Mn–Ti–Si–V–P–B steel after neutron irradiation at a temperature of 440–600°C to damaging doses of 36–94dpa10.1134/S0031918X16060090 ↗
5. Vacancy void growth rate as a function of the neutron irradiation parameters at the initial stage of transient swelling10.1134/S0036029519030078 ↗
6. Model of the final stage of nonstationary radiation swelling of metals10.1134/S0031918X20070042 ↗
7. The evolution of helium-vacancy bubbles in austenitic steels under neutron irradiation10.1016/j.jnucmat.2021.152915 ↗
8. Rate theory model of radiation-induced swelling in an austenitic stainless steel10.3390/jne2040034 ↗
9. Effect of neutron irradiation on the mechanical properties, swelling and creep of austenitic stainless steels10.3390/ma14102622 ↗
10. Swelling and He-embrittlement of austenitic stainless steels and Ni-alloys in nuclear reactors10.3390/met12101692 ↗
11. Simplified atomistic based kinetic model for swelling prediction10.1016/j.jnucmat.2023.154640 ↗
12. Software package acdam-2.0 for investigation of nuclear physical properties of materials in conditions of neutron irradiation
13. Nuclear physical properties of austenitic nickel and manganese steels under neutron irradiation in nuclear fission (fast) and fusion reactors
14. Influence of dislocation and dislocation loop biases on microstructures simulated by rate equation cluster dynamics10.1016/j.jnucmat.2015.09.046 ↗
15. Cluster-dynamics modelling of defects in α-iron under cascade damage conditions10.1016/j.jnucmat.2008.08.010 ↗
16. Primary radiation damage: a review of current understanding and models10.1016/j.jnucmat.2018.10.027 ↗
17. The effect of irradiation conditions on generation of defects and their clusters
18. Quantifying defect production in solids at finite temperatures: thermally-activated correlated defect recombination corrections to dpa (CRC-DPA)10.1016/j.jnucmat.2023.154292 ↗
19. The theory of sink strengths
20. Dislocation sinks efficiency for self-point defects in iron and vanadium crystals10.1134/S2075113315020161 ↗
21. Ferromagnetic effects on non-arrhenius diffusion of single interstitial helium solute in BCC Fe10.1016/j.jnucmat.2019.07.014 ↗
22. Thermal surface free energy and stress of iron10.1038/srep14860 ↗
23. Irradiation performance of cladding and structural steels in liquid metal reactors10.1002/9783527603978.mst0110 ↗
24. Solute–< 111>interstitial loop interaction in $α$-Fe: a DFT study10.1016/j.jnucmat.2017.10.070 ↗
25. Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments10.1016/j.actamat.2020.07.060 ↗