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UKAEA-CCFE-PR(25)2902023
The augmentation of mechanical properties of reduced activation ferritic martensitic steels through the introduction of creep resistant nano-oxide particles produces a class of oxide dispersion strengthened steels, which have attracted significant interest as candidates for first wall supporting structural materials in future nuclear fusion reac…
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UKAEA-CCFE-PR(25)2892023
This paper reports the first experiment carried out in deuterium–tritium addressing the integration of a radiative divertor for heat-load control with good confinement. Neon seeding was carried out for the first time in a D–T plasma as part of the second D–T campaign of JET with its Be/W wall environment. The technical difficulties linked to …
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UKAEA-CCFE-PR(24)2462023
Ion Cyclotron wave (IC) assisted breakdown would be important for reducing risks to plasma initiation during the ITER pre-fusion operation phase under difficult vessel conditions. Hence, studies were performed at JET, at ITER relevant loop electric field — and in a regime, and , where plasma breakdown had not previously been achieved on JE…
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UKAEA-CCFE-PR(23)1802023
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UKAEA-CCFE-PR(24)2442022
Zirconium alloys are widely used as the fuel cladding material in pressurised water reactors where a significant population of defects and dislocations is produced by exposure to neutrons. We present and interpret synchrotron microbeam X-ray diffraction measurements of proton- irradiated Zircaloy-4, where we identify a transient peak and the sub…
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UKAEA-CCFE-CP(24)072022
Future fusion reactors using deuterium-tritium fuel will create high fluences of high-energy neutrons inside and around the reactor vessel. As well as causing material damage, fusion neutrons will activate materials, the decay of which leads to radiation fields in and around the reactor after shutdown. Gamma-ray emission from activated materials…
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UKAEA-CCFE-PR(23)1492022
Materials subjected to irradiation damage often undergo local changes in the microstructure that effect the expected performance. To investigate those changes, this work proposes a novel approach to detect strain localisation caused by irradiation-induced damage in nuclear materials on the microstructural level, conside…
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UKAEA-CCFE-CP(23)592022
Investigations were undertaken into the thermal treatment of beryllium and tungsten to see if these materials can be detritiated in the Material Detritiation Facility (MDF) at UKAEA, allowing for the declassification of intermediate level waste (ILW) to low level waste (LLW). When heated in oxygen, both tungsten and beryllium readily oxidise, wi…
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UKAEA-CCFE-PR(23)1342022
During operation, structural components made of zirconium alloys are subject to neutron irradiation, which leads to the displacement of zirconium atoms from their lattice sites, the production of self-interstitials and vacancies, and eventually dislocation loops. This process can lead to deleterious effects such as irradiation growth, creep and …
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UKAEA-CCFE-PR(23)1332022
Hard-facing alloys in nuclear applications must remain resistant to deformation and wear, whilst also minimising transmutation to problematic elements during service. To this end, the Fe-based alloy RR2450 has been developed to potentially replace Co-based hard-facing alloys. RR2450 is a complex multi-phase stainless steel alloy showing an unusuall…
Showing 11 - 20 of 43 UKAEA Paper Results