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The Laws of Nuclear Heat Transfer
Published in Robert E. Masterson, Nuclear Reactor Thermal Hydraulics, 2019
Many heat transfer processes encountered in nuclear science and engineering are based on the same underlying principles. It is sometimes instructive to draw a map of these various processes and relate them to each other by “connecting the dots.” A map such as this is shown in Figure 10.36. Notice that the field of reactor thermal-hydraulics requires a comprehensive knowledge of thermodynamics and material science, as well as all three forms of nuclear heat transfer: conduction, convection, and radiation. Additional maps of this type can be found on the Internet. Now, let us take a moment to review what we have just learned.
Analyses of Critical Hydrogen Enrichment in PWR Containment Compartments
Published in Nuclear Science and Engineering, 2023
E. Schmidt, N. Reinke, M. Freitag, M. Sonnenkalb
COCOSYS (Ref. 9) is a lumped parameter code to analyze all relevant processes occurring in a light water reactor containment during severe accidents. The main aspects are thermal hydraulics, aerosol and fission product behavior, corium-concrete interaction, and fission product release from the molten corium concrete mixture in the cavity. In this benchmark, only the thermal-hydraulic module of COCOSYS (THY) is used. The general approach is constituted of dividing the region of interest, i.e., the TTV of the THAI facility, into several zones, connecting them by junctions or flow paths, and defining boundary conditions representing the structures. Focusing on thermal hydraulics, the nodes contain steam, water, and noncondensable gases. They exchange thermal energy with adjacent structures through several heat transfer mechanisms. Convection, either free or forced, and thermal radiation from gas to wall determine for example the degree of superheating of the atmosphere or the volume condensation rate (fog formation rate). Condensation of steam determines for example the difference between the saturation temperature of the atmosphere and the wall surface. It is based on the Stephan’s law with an analogy to the convection heat transfer.
Selected papers from the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18)
Published in Nuclear Science and Engineering, 2020
NURETH-18 was held in Portland, Oregon, August 18–23, 2019. The meeting was sponsored by the American Nuclear Society and was cosponsored by a number of industrial, governmental, and educational organizations. NURETH-18 had 156 sessions over four days. In total, 604 full papers were presented as part of the technical program, along with 3 panel sessions and 17 technical keynote addresses. Topics addressed during NURETH-18 included fundamental thermal hydraulics, computational thermal hydraulics, verification and validation, safety of existing reactors, severe accidents, and thermal hydraulics in advanced reactors. The program also included emerging topical areas of interest such as the thermal hydraulics of TREAT, fluid–structure interactions, the benchmark study of the accident at the Fukushima plant, and the thermal hydraulics of fluoride salt–cooled high-temperature reactors.
Foreword: Selected papers from the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18)
Published in Nuclear Technology, 2020
NURETH-18 was held in Portland, Oregon, August 18–23, 2019. The meeting was sponsored by the American Nuclear Society and was cosponsored by a number of industrial, governmental, and educational organizations. NURETH-18 had 156 sessions over four days. In total, 604 full papers were presented as part of the technical program, along with 3 panel sessions and 17 technical keynote addresses. Topics addressed during NURETH-18 included fundamental thermal hydraulics, computational thermal hydraulics, verification and validation, safety of existing reactors, severe accidents, and thermal hydraulics in advanced reactors. The program also included emerging topical areas of interest such as the thermal hydraulics of TREAT, fluid–structure interactions, the benchmark study of the accident at the Fukushima plant, and the thermal hydraulics of fluoride salt–cooled high-temperature reactors.