The design and implementation of an in-situ mechanical loading apparatus used during proton-irradiations
Source abstract
Abstract
The Proton Irradiation Tensile Rig (PITR) is a linear tensile testing apparatus developed to conduct in-situ proton irradiation studies at the Reactor Materials Testing Laboratory at Queen`s University. This apparatus, capable of controlling sample temperature, stress, and proton flux, aims to closely replicate the conditions of materials inside of a nuclear power reactor and provide means to research and develop a mechanistic understanding of material deformation under irradiation. A commissioning test was conducted on pure zirconium foil in which the in-situ creep rate was measured at a variety of applied proton flux while maintaining a constant temperature of 350 °C and a constant load of 30 MPa. This paper details the apparatus design and implementation as well as results and discussion from the commissioning test.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (38)
Show source-provided references
1. Effect of neutron irradiation on the tensile properties of zircaloy-2 and zircaloy-410.1016/0022-3115(72)90099-2 ↗
2. Strength and ductility of neutron irradiated and textured zircaloy-210.1520/STP32125S ↗
3. A review of microstructure evolution in zirconium alloys during irradiation10.1016/0022-3115(88)90093-1 ↗
4. In-reactor deformation of cold-worked Zr–2.5Nb pressure tubes
5. Irradiation creep and growth of zirconium alloys: a critical review10.1016/j.jnucmat.2019.04.021 ↗
6. Surface, structural and tensile properties of proton beam irradiated zirconium10.1016/j.nimb.2015.12.001 ↗
7. Irradiation creep and irradiation stress relaxation of 316 and 304L stainless steels in thermal and fast neutron spectrum reactors
8. Principles and practice of a bellows-loaded compact irradiation vehicle10.1016/j.jnucmat.2013.03.096 ↗
9. Irradiation creep and growth during proton and neutron bombardment of zircaloy-2 plate
10. 2016
11. Opportunities and limitations for ion beams in radiation effects studies: bridging critical gaps between charged particle and neutron irradiations10.1016/j.scriptamat.2017.06.041 ↗
12. Intermediate energy proton irradiation: rapid, high-fidelity materials testing for fusion and fission energy systems10.1016/j.matdes.2020.109445 ↗
13. Microstructural examination of neutron, proton and self-ion irradiation damage in a model Fe9Cr alloy10.1016/j.jnucmat.2020.152130 ↗
14. The irradiation creep of nickel and AISI 321 stainless steel during 4 MeV proton bombardment10.1016/0022-3115(77)90066-6 ↗
15. Proton irradiation creep of FM steel T9110.1016/j.jnucmat.2015.01.023 ↗
16. In situ proton irradiation creep of ferritic–martensitic steel T91
17. Advantages and disadvantages of the various particle types
18. In situ creep measurements on micropillar samples during heavy ion irradiation10.1016/j.jnucmat.2014.03.037 ↗
19. Direct measurements of irradiation-induced creep in micropillars of amorphous Cu56Ti38Ag6, Zr52Ni48, Si, and SiO210.1063/1.4905019 ↗
20. Deformation of zirconium irradiated by 4.4 MeV protons at 347K10.1016/j.jnucmat.2004.01.017 ↗
21. Digital image correlation10.1016/S1369-7021(10)70235-2 ↗
22. Distortion of Digital Image Correlation (DIC) Displacements and Strains from Heat Waves
23. 12.2.1 Cross Section
24. SRIM – The stopping and range of ions in matter
25. Conditions for effects of radiation pulsing10.1016/S0022-3115(02)01133-9 ↗
26. Pulsed flux effects on radiation damage10.1016/0022-3115(84)90628-7 ↗
27. Effects of pulsed dual-ion irradiation on phase transformations and microstructure in Ti-modified austenitic alloy10.1016/0022-3115(83)90018-1 ↗
28. The activation cross section measurements of proton-induced reactions on Li and Ta in the energy region 12.5–34 MeV10.1016/j.nuclphysa.2021.122310 ↗
29. Hasselkamp · 1992
30. G. Choppin, J.O. Liljenzin, J. Rydberg, and C. Ekberg, “10.5 Elastic scattering,” in Radiochemistry and Nuclear Chemistry, Elsevier. [Online]. Available: https://app.knovel.com/hotlink/pdf/id:kt00BWZKA3/radiochemistry-nuclear/elastic-scattering.
31. Chen · 2017
32. The effect of substrate texture and oxidation temperature on oxide texture development in zirconium alloys10.1016/j.jnucmat.2016.10.037 ↗
33. The effect of neutron irradiation on the tensile properties of zircaloy-210.1016/0022-3115(60)90059-3 ↗
34. Adamson · 2009 · 39
35. Creep of zirconium and zirconium alloys
36. The Irradiation creep and growth phenomena10.1016/0022-3115(88)90083-9 ↗
37. 14.2 Irradiation creep
38. Uniaxial in-reactor creep of zircaloy-2: stress, flux, and temperature dependence10.13182/NT83-A33106 ↗