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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
D. D. Lisowski, T. C. Haskin, A. Tokuhiro, M. H. Anderson, M. L. Corradini
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 75-87
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-A16993
Articles are hosted by Taylor and Francis Online.
Recent design efforts have used the reactor cavity cooling system (RCCS) for passive decay heat removal in the Next Generation Nuclear Plant. Employing a series of riser tubes and cooling panels that line the containment walls, the RCCS can provide an ultimate heat sink for decay power removal from the system without the need for AC power. With vessel wall temperatures expected to reach 450°C, intuition suggests that radiation will be the dominant mode of heat transfer. However, the authors show that several factors can alter these modes; variations in cavity height, riser tube geometry, and vessel heat flux may have significant roles in the heat removal by the RCCS.The authors have constructed a one-quarter-scale water-cooled experimental facility at the University of Wisconsin-Madison that is based on available open literature of the General Atomics modular high-temperature gas-cooled reactor, with a three-riser tube and cooling panel test section representing a 5-deg slice of the full-scale design. Under prototypic heat flux conditions, a series of scoping tests with linear and asymmetrically skewed heating profiles were performed to investigate the split in flow distribution among the parallel channels. Numerical results, using RELAP5 models and FLUENT simulations, provide a comparison to experimental data sets and insight into the split among heat transfer modes present in the cavity.Application of these passive decay heat removal systems demands a pragmatic approach that can account for the irregularities and nonuniformities present in a real design. In areas of blocked views, such as near support structures and primary cooling pipes, convection can provide a mechanism to smooth the otherwise skewed radiative heat flux for heat transfer from the reactor pressure vessel walls to the cooling panels. Integral to the design of the RCCS, the cooling fins serve to protect the cavity wall while adding additional pathways for heat dissipation by conduction into the cooling tubes.