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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
X-energy, Dow apply to build an advanced reactor project in Texas
Dow and X-energy announced today that they have submitted a construction permit application to the Nuclear Regulatory Commission for a proposed advanced nuclear project in Seadrift, Texas. The project could begin construction later this decade, but only if Dow confirms “the ability to deliver the project while achieving its financial return targets.”
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.