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Division Spotlight
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.
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.
Parvez Salim, Yassin A. Hassan
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 275-285
Technical Paper | RELAP/MOD2 / Nuclear Safety | doi.org/10.13182/NT90-A34393
Articles are hosted by Taylor and Francis Online.
A best-estimate small-break loss-of-coolant accident (SBLOCA) analysis of a four-loop pressurized water reactor nuclear power plant is conducted using the computer code RELAP5/MOD2. A plant-specific RELAP5 model is developed, and steady-state operating conditions are calculated. The steady-state model is then employed to obtain SBLOCA scenarios for different break sizes. Transients resulting from the different breaks are studied to determine the limiting break size and obtain comprehensive transient scenarios. The effect of the hydraulic diameter on the transient behavior, related to the steam generator U-tubes, is also observed. The relationship between the break size and the peak cladding temperature is obtained. The study indicates that as the break size increases, a smaller core inventory instigates heatup during core boil-off.
