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The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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Nuclear Science and Engineering
Fusion Science and Technology
Study: New U.K. nuclear likely to be lower carbon source than solar or wind
A recent study of life cycle carbon emissions at the United Kingdom’s Hinkley Point C nuclear plant finds that the facility, now under construction in Somerset, England, is likely to produce less CO2 over its lifetime than either solar or wind power.
According to the 70-page analysis—prepared by environmental consultancy Ricardo Energy & Environment for NNB Generation Company HPC Limited, the holding company for the Hinkley Point project—lifetime emissions from Hinkley Point C are likely to be about 5.5g CO2e per kWh. That amount also holds for the proposed Sizewell C plant, the study concludes. (The two 1,630-MWe EPRs at Hinkley Point C are currently scheduled to begin commercial operation in 2026 and 2027.)
Marti Jeltsov, Walter Villanueva, Pavel Kudinov
Nuclear Technology | Volume 190 | Number 1 | April 2015 | Pages 1-10
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT14-8
Articles are hosted by Taylor and Francis Online.
Risks related to sloshing of liquid metal coolant due to seismic excitation need to be investigated. Sloshing effects on reactor performance include first, fluid-structure interaction and second, gas entrapment in the coolant with subsequent transport of void to the core region. While the first can hypothetically lead to structural damage or coolant spill, the second increases the risk of a reactivity insertion accident and/or local dryout of the fuel. A two-dimensional computational fluid dynamics study is carried out in order to obtain insights into the modes of sloshing depending on the parameters of seismic excitation. The applicability and performance of the numerical mesh and the Eulerian volume of fluid method used to track the free surface are evaluated by modeling a simple dam break experiment. Sloshing in the cold plenum free surface region of the European Lead-cooled SYstem (ELSY) conceptual pool-type lead-cooled fast reactor (LFR) is studied. Various sinusoidal excitations are used to imitate the seismic response at the reactor level. The goal is to identify the domain of frequencies and magnitudes of the seismic response that can lead to loads threatening the structural integrity and possible core voiding due to sloshing. A map of sloshing modes has been developed to characterize the sloshing response as a function of excitation parameters. Pressure forces on vertical walls and the lid have been calculated. Finally, insight into coolant voiding has been provided.