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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
Standards Program
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
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
Heikki Kantee, Harri Tuomisto, Vesa Yrjölä
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 308-315
Technical Paper | RELAP/MOD2 / Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34396
Articles are hosted by Taylor and Francis Online.
The RELAP5/MOD2 computer code has been extensively utilized in calculation of thermal-hydraulic sequences concerning the pressurized thermal shock safety issue in the Loviisa 1 nuclear power plant. The cases analyzed feature stuck-open pressurizer safety valve sequences, small hot-leg breaks, steam line breaks, and, in one case, a primary-secondary leakage. The main purpose of these analyses is to validate and compare the results from the full-scale Loviisa training simulator analyses. The RELAP5 model is made to the detail allowed by the computer. It includes a description of primary and secondary circuits as well as modeling of the emergency core cooling and control systems. Single-phase thermal stratification and mixing are essential phenomena when pressurized thermal shock sequences are analyzed. The capabilities of the large system analysis code to predict these phenomena in the reactor circuit are discussed.
