Change in the density of single-crystal tungsten during neutron irradiation

Bykov, V. N.; Birzhevoi, G. A.; Zakharova, M. I.

doi:10.1007/bf01116968

Cited by 2 publications

(3 citation statements)

References 3 publications

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“…Investigations on the damage mechanisms, damage recovery, defect types, and microstructural changes have been continuously performed since the late 1950s ( ). The same is true for studies on the neutron irradiation induced change of mechanical and physical properties ( [144][145][146][147][148][149][150][151][152][153][154][155][156][157][158][159][160]) as well as the volumetric change -the so-called swelling ( [161,162]). Transmutation is also a typical effect of neutron-nuclei interaction, which changes the chemical composition of materials.…”

Section: Publications On the Effect Of Irradiation And Plasma Interac...mentioning

confidence: 99%

Behavior of tungsten under irradiation and plasma interaction

Rieth

Doerner

Hasegawa

et al. 2019

Journal of Nuclear Materials

145

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Section: Publications On the Effect Of Irradiation And Plasma Interac...mentioning

confidence: 99%

Behavior of tungsten under irradiation and plasma interaction

Rieth

Doerner

Hasegawa

et al. 2019

Journal of Nuclear Materials

145

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Section: Tungsten Swellingmentioning

confidence: 99%

“…A comprehensive review of the effects of irradiation on tungsten is provided by Reith [16] who identified two key papers on swelling by Matolich [17] and Bykov [18]. The single crystal data from Bykov (as summarised by figure 1 in [18]) shows that under a fluence of 1.4e22 n/cm², density changes of 1.2% were recorded at 500°C reducing to ~0.15% at 2000°C. The reactor used for these tests is not specified so an estimated equivalent dpa value of 1.5 dpa is calculated using the approximate 0.8x10 22 n/cm²/dpa conversion factor described above.…”

Section: Tungsten Swellingmentioning

confidence: 99%

Towards reliable design-by-analysis for divertor plasma facing components—Guidelines for inelastic assessment (part II: irradiated)

Fursdon

You

2020

Fusion Engineering and Design

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This paper gives guidelines for assessing the structural integrity of plasma facing components (PFC)when irradiated to the levels expected in DEMO after two full power years. The paper is part II of a 3-part paper describing the EuroFusion DEMO Divertor group (WPDIV) Inelastic Analysis procedure (IAP), created to improve the assessment of PFCs, and specifically those constructed from tungsten armour cooled by CuCrZr heat sink (with Copper interlayer). The paper first provides a recap of the IAP methodology detailed in the part 1 paper and then presents a detailed review of the limited relevant irradiated materials data on material properties (thermal conductivity, swelling and stressstrain curves) and materials limit data (rupture-strain, fracture-toughness and fatigue strength). The data is used in an example structural integrity assessment estimate of an ITER-like divertor "monoblock" PFC (tungsten block with through CuCrZr pipe) when irradiated to ~14dpa (CuCrZr) & ~ 4dp (tungsten). The assessment uses IAP methodologies to determine the susceptibility of the design to failure by exhaustionof-ductility, fast-fracture, fatigue and ratcheting in the CuCrZr pipe, exhaustion of ductility in the copper interlayer and brittle fracture in the tungsten armour. These methodologies ensure that contributions from changes in both material limit-levels and material properties are included. The paper documents the extrapolations required to extend the existing irradiated materials data to the expected dpa and temperature range. The assessment exposes significant shortfalls in the monoblock type design in coping with the drastic reduction in copper ductility and tungsten strength caused by irradiation. This illustrates that maintaining structural integrity when irradiated poses a far more stringent constraint on a PFC design than the un-irradiated condition, and as such should be given priority in future design studies. Although the prime aim of the paper is to present assessment methodologies, it also helps identify the key gaps in irradiated materials property data (and emphasise the severe need for a fully populating irradiated materials database).

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Change in the density of single-crystal tungsten during neutron irradiation

Cited by 2 publications

References 3 publications

Behavior of tungsten under irradiation and plasma interaction

Behavior of tungsten under irradiation and plasma interaction

Towards reliable design-by-analysis for divertor plasma facing components—Guidelines for inelastic assessment (part II: irradiated)

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