ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Wyoming as a hub for new nuclear manufacturing and microreactor deployment?
A 60-year-old Wyoming industrial machinery company is partnering with nuclear innovator BWX Technologies to deploy 50-megawatt microreactors in America’s heartland over the coming years to provide carbon-free heat and power for industrial users.
A. Kenigsberg, D. Hasan, E. Elias
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 219-224
Technical Paper | Reactor | doi.org/10.13182/NT80-A32525
Articles are hosted by Taylor and Francis Online.
A hypothetical accident is analyzed, in which an external (outof-plant) natural or man-made event causes a loss-of-coolant accident after penetrating the containment wall The computer codes CONTEMPT and RELAP4 have been used to study the containment thermal-hydraulic behavior during the accident. The radioactive materials outflow rate is calculated for a wide range of anticipated breach sizes, assuming perfect mixing in the air-steam-water mixture in the containment building. Typically, there is only a low pressure buildup in the initially breached containment. Therefore, the calculated fission product release rate is lower than the predicted rate in case the containment fractures in a later phase of the accident.