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Association of Augmentation Index With Cerebral Small Vessel Disease: A Systematic Review and Meta-Analysis. [PDF]
Am J HypertensKarachalias F +8 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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An online sample size calculator for designing partially clustered trials. [PDF]
Clin TrialsLange KM +3 more
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Nuclear Engineering and Design, 1987
Abstract A series of experiments have been performed which help to provide fundamental understanding of the phenomena which are important to the analysis of a PWR pressurizer. The transients considered include insurges to a partially-full tank, outsurges, insurges to a tank with hot walls, empty tank insurges, and combined insurges and outsurges. The
Sang-Nyung Kim, Peter Griffith
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Abstract A series of experiments have been performed which help to provide fundamental understanding of the phenomena which are important to the analysis of a PWR pressurizer. The transients considered include insurges to a partially-full tank, outsurges, insurges to a tank with hot walls, empty tank insurges, and combined insurges and outsurges. The
Sang-Nyung Kim, Peter Griffith
openaire +1 more source
Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, 2014
Corrosion products deposit on Pressurized Water Reactor (PWR) fuel rod cladding surfaces and can create a number of issues including increased cladding temperature, elevated cladding corrosion, and the precipitation of boron species within the deposits.
W. A. Byers +3 more
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Corrosion products deposit on Pressurized Water Reactor (PWR) fuel rod cladding surfaces and can create a number of issues including increased cladding temperature, elevated cladding corrosion, and the precipitation of boron species within the deposits.
W. A. Byers +3 more
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A Small PWR-Core Physical Calculation Based on PWR-Core Analysis Code CORAL
Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, 2021Abstract Three dimensional PWR-core analysis code CORAL is developed by Wuhan Second Ship Design and Research Institute. This code provides basic functions including three-dimensional power distribution, fine power reconstruction, fuel temperature distribution, critical search, control rod worth, reactivity coefficients, burnup and ...
Wen Yang, Lun Zhou, Junrong Qiu, Yun Tai
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Energy Policy, 2013
Abstract The construction time of PWRs is studied considering published data about nuclear power plants in the world. For the 268 PWRs in operation in 2010, the mode of the construction time distribution is around 5–6 years, and 80% of the plants were built in less than 120 months.
João M.L. Moreira +2 more
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Abstract The construction time of PWRs is studied considering published data about nuclear power plants in the world. For the 268 PWRs in operation in 2010, the mode of the construction time distribution is around 5–6 years, and 80% of the plants were built in less than 120 months.
João M.L. Moreira +2 more
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PWR Supplemental Surveillance Program
2014A pressurized water reactor (PWR) supplemental surveillance program (PSSP) is being designed to provide high-fluence reactor vessel material embrittlement data for the operating U.S. PWRs. Peak reactor pressure vessel (RPV) fluence levels as high as 7 × 1019n/cm2 (E > 1.0 MeV) will be attained as PWRs operate to 60 years and potentially beyond ...
J. Brian Hall +3 more
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Safety Assessment of Advanced PWR
2018 International Conference on Power Generation Systems and Renewable Energy Technologies (PGSRET), 2018In the present study, safety assessment of advanced light water nuclear reactor has been performed using the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) methodology. This methodology is considered to be a tool to check the nuclear energy system (NES) sustainability in seven different areas. Out of these seven areas, one
Suhail Ali +4 more
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