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From Processing to Simulated In-Reactor Performance of Zr Cladding. [Clear]

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48 Simultaneous Corrosion/Irradiation Testing in Lead and Lead-Bismuth Eutectic: The Radiation Decelerated Corrosion Hypothesis (RC-3) EPSRC
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51 Radiation Damage in Nanoporous Nuclear Materials EPSRC
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52 Developing high Co-containing Ni-based superalloys with improved oxidation behaviour for future jet-engine applications EPSRC
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55 Mechanistic understanding the mechanism of hydrogen-facilitated stress corrosion cracking - DiffH-SCC Horizon Europe Guarantee
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56 Understanding the In-Reactor Performance of Advanced Ceramic Cladding Materials EPSRC
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57 Development of strong, formable, stainless and low-cost magnesium alloys for next generation cars UKRI
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