Effects of neutron irradiation at 450°C and 16 dpa on the properties of various commercial copper alloys

Brager, H.R.; Heinisch, Howard L.; Garner, F.A.

doi:10.1016/0022-3115(85)90234-x

Cited by 63 publications

(9 citation statements)

References 3 publications

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“…∼50 MPa [63]. Glidcop alloys keep significant yield strength after irradiation up to ∼16 dpa at ∼450 • C in fast neutron reactor; the electrical conductibility remains ∼80% of the one of the OFHC Cu [64].…”

Section: Reliability and Materials Issues: Functional Materials/the Exmentioning

confidence: 98%

Efficiency and availability driven R&D issues for DEMO

Paméla

Bécoulet

Borba³

et al. 2009

Fusion Engineering and Design

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Section: Reliability and Materials Issues: Functional Materials/the Exmentioning

confidence: 98%

Efficiency and availability driven R&D issues for DEMO

Paméla

Bécoulet

Borba³

et al. 2009

Fusion Engineering and Design

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“…[17]; (ii) Glidcop demonstrates greater tolerance to damage compared to CuCrZr, with experimentally observed improvement in yield strength for larger damage rates and temperatures. An appropriate damage limit is thus �15dpa [18].…”

Section: ) Calculation Of Materials Damagementioning

confidence: 99%

The influence of injector design on neutral beam optimisation for DEMO

Surrey

Benn

Jenkins

et al. 2011

2011 IEEE/NPSS 24th Symposium on Fusion Engineering

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The requirements for neutral beam injection (NBf) on DEMO are assessed and the consequences for the design of the injectors discussed. Optimization of current drive requires NBf within a 2m x 2m envelope in the plasma poloidal cross section at large tangency radii. This is compatible with beam lines of 20m length and moderate high voltage stand-off distances between injectors. However, q-profile control will necessitate at least three beam lines of different injector types and may not be compatible with shinethrough power limits.Material irradiation studies show that there is no significant design issue for radial distances greater than 3m from the tokamak wall.

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“…to 40% compared to thermal-annealed control specimens following irradiation to 10 to 15 dpa at temperatures of 450°C [28] and 385°C [29].…”

Section: Discussionmentioning

confidence: 99%

Radiation-enhanced recrystallization in copper alloys

Zinkle

Kulcinski

Mansur

1986

Journal of Nuclear Materials

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Two high-strength copper alloys, cold-worked-and-aged AHZIRC (Cu-Zr) and AMAX-MZC (Cu-Cr-Zr-Mg), were irradiated with 14-MeV Cu ions to a damage level of 10 dpa at temperatures of 100 to 500°C. Cross-section examination of the irradiated foils using electron microscopy revealed signs of irradiation-enhanced recrystallization for irradiation temperatures above 300°C. The recrystallization temperature for both alloys is about 450°C during thermal annealing for a time similar to the ionirradiation time -1.5 h. A simplified analysis of the results suggests that the accelerated recrystallization kinetics is due to radiationenhanced diffusion (RED). This process may restrict the maximum operating temperature of fusion reactor components that incorporate these types of alloys to temperatures as low as 200°C.

show abstract

Effects of neutron irradiation at 450°C and 16 dpa on the properties of various commercial copper alloys

Cited by 63 publications

References 3 publications

Efficiency and availability driven R&D issues for DEMO

Efficiency and availability driven R&D issues for DEMO

The influence of injector design on neutral beam optimisation for DEMO

Radiation-enhanced recrystallization in copper alloys

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