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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Argonne opens registration for D&D training course
Registration is open for Argonne National Laboratory’s Facility Decommissioning Training Course, a four-day instruction designed for those responsible for the decontamination and decommissioning of nuclear facilities and who are looking to understand the full breadth and depth of the D&D processes.
The next session will be held July 16–19 in Santa Fe, N.M. Information on the course and how to register can be found here.
Rodolfo Vaghetto, Yassin A. Hassan
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 282-293
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-130
Articles are hosted by Taylor and Francis Online.
The Very High Temperature Gas-Cooled Reactor (VHTR) is one of the next-generation nuclear reactors designed to achieve high temperatures to support industrial applications and power generation. Because of the high temperature reached during normal operation, new safety features were added to its design. The reactor cavity cooling system (RCCS) is a passive safety system that will be incorporated in the VTHR. The system was designed to remove the heat from the reactor cavity and maintain the temperature of structures and concrete walls under desired limits during normal operation (steady state) and accident scenarios. A small-scale (1:23) water-cooled experimental facility was scaled, designed, and constructed in order to study the thermal-hydraulic phenomena taking place in the RCCS during steady-state and transient conditions. The facility represents a portion of the reactor vessel with nine stainless steel coolant risers and utilizes water as coolant. The facility was equipped with instrumentation to measure temperatures and flow rates. A steady-state experimental run was conducted to study the behavior of the coolant under this condition. The experimental results obtained confirmed the capabilities of the system in removing the heat from the cavity and helped in identifying phenomena that may occur in this type of passive system.