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Chernobyl at 40 years: Looking back at Nuclear News
Sunday, April 26, at 1:23 a.m. local time will mark 40 years since the most severe nuclear accident in history: the meltdown of Unit 4 at the Chernobyl nuclear power plant in Ukraine, then part of the Soviet Union.
In the ensuing four decades, countless books, documentaries, articles, and conference sessions have examined Chernobyl’s history and impact from various angles. There is a similar abundance of outlooks in the archives of Nuclear News, where hundreds of scientists, advocates, critics, and politicians have shared their thoughts on Chernobyl over the years. Today, we will take a look at some highlights from the pages of NN to see how the story of Chernobyl evolved over the decades.
S. Smolentsev
Fusion Science and Technology | Volume 79 | Number 3 | April 2023 | Pages 251-273
Technical Paper | doi.org/10.1080/15361055.2022.2116905
Articles are hosted by Taylor and Francis Online.
The successful development of robust breeding blanket systems will strongly rely on computational tools for predicting the complex behavior of the electrically conducting liquid-metal (LM) breeder flowing in the complex-shaped blanket ducts in the presence of a strong plasma-confining magnetic field, volumetric heating, and tritium generation. Associated transport processes involve magnetohydrodynamic (MHD) flows, heat transfer, corrosion, and tritium transport. This paper is an overview of past and present efforts in the development, application, and verification and validation (V&V) of such computational tools. As a result of the ongoing campaign on V&V of computer codes for LM blankets, the international fusion community has identified several candidates that promise to become real blanket design and analysis tools in the near future. Among them are HIMAG, MHD-UCAS, COMSOL Multiphysics, ANSYS FLUENT, ANSYS CFX, and OpenFOAM. The progress, over the last decade, in the application of such codes in blanket studies is tremendous. This is illustrated with two examples for a dual-coolant lead-lithium (DCLL) blanket: (1) integrated computer modeling for the recently designed DCLL blanket in the United States and (2) application of the code MHD-UCAS to the analysis of PbLi flows and heat transfer in a generic DCLL blanket prototype at high Hartmann (Ha ~ 104) and Grashof numbers (Gr ~ 1012). This paper also presents an approach to the development of a new integrated computational tool called the virtual dual-coolant lead-lithium (VDCLL) blanket, which elaborates the existing U.S. MHD code HIMAG.