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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
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Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Francesco D'auria, Giorgio Maria Galassi
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 340-355
Technical Paper | RELAP/MOD2 / Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34399
Articles are hosted by Taylor and Francis Online.
Assessment of the RELAP5/MOD2 code on the basis of experiments performed in a pressurized water reactor simulator, the LOBI/MOD2 facility at the European Research Center of Ispra in Italy is reported. In particular, significant experience gained in the analysis of two small-break loss-of-coolant accidents (tests A2-81 and A1-83), a steam generator tube rupture (test BL-21), a natural circulation (test A2-77A), and four transients (tests A2-90, BT-00, BT-01, and BT-03) is discussed.
