Corrosion fatigue life prediction of multiple austenitic stainless steel grades in high-temperature, high-pressure water environments using a GA-optimized neural network. [PDF]
Sci RepBhardwaj HK, Shukla M.
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A multidisciplinary framework from reactors to repositories for evaluating spent nuclear fuel from advanced reactors. [PDF]
Sci RepWainwright HM +6 more
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An open time-series simulated dataset covering various accidents for nuclear power plants. [PDF]
Sci Data, 2022 Qi B +5 more
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Prediction of spallation induced transmutation rates for long-lived fission products via proton accelerator. [PDF]
Sci RepTukharyan G +4 more
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Thermodynamic Analysis and Crystallographic Properties of MFe2O4, MCr2O4 and MAl2O4 (M = Fe, Ni, Zn) Formed on Structural Materials in Pressurized Water Reactor Primary Circuit under Zinc and Zinc-aluminum Water Chemistry. [PDF]
Entropy (Basel), 2022 Jiao Y, Zhang S, Tan Y.
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A transformer-XGBoost based model to fault diagnosis for CPR1000. [PDF]
Sci RepPeng Z +6 more
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Study on the Thermophysical Properties of 80% 10B Enrichment of B4C. [PDF]
Materials (Basel), 2023 Lv Z +9 more
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SMR/AMR waste assessment: an analysis methodology proposal [PDF]
International audienceThe paper focuses on type of waste produced by power reactors and SMR/AMR (Small Modular Reactor, Advanced Modular Reactor). An assessment methodology is proposed to analyse and compare advantages and disadvantages of the different ...
Mandoki, Robert +4 more
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Numerical simulation of heat dissipation characteristics in PWR high-pressure coolant pipes during cold shutdown. [PDF]
Sci RepTang F +5 more
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Testing the feasibility of multi-modular design in an HTR-PM nuclear plant. [PDF]
Nat CommunDong Z +6 more
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