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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
Yoshiyuki Kataoka, Tohru Fukui, Shigeo Hatamiya, Toshitsugu Nakao, Masanori Naitoh, Isao Sumida
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 386-396
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34722
Articles are hosted by Taylor and Francis Online.
To evaluate the heat removal capability of an external water wall-type containment vessel, which is a passive system for containment cooling, thermal-hydraulic behavior in the suppression and outer pools has been examined experimentally. The following results are obtained: 1. A thermal stratification boundary, which separates the pools into an upper high-temperature region and a lower low-temperature region, is observed just below the vent outlet. 2. The natural-convection heat transfer coefficients (HTCs) for the downward and upward flows that appear inside and outside the primary containment vessel wall are measured. These values can be expressed by Nu = 0.13Ra1/3. 3. The condensation HTCs in the presence of non-condensable gas, which affect heat transfer between the wet well and the outer pool, are measured along the long wall. The vertical variations of the condensation HTCs are within 10% of the averaged coefficients, and the averaged coefficients can be expressed by hm = 0.43(ma/ms)-0.8, where hm (kW/m2·K is the condensation HTC and (ma/ms) is the mass ratio of noncon-densable gas and steam. 4. The capability for decay heat removal in the external water wall-type containment vessel for a 600-MW(electric) plant is evaluated based on these results and is found to be large enough.