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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Yoshihiro Nakane, Teruo Abe, Hiroshi Nakashima
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 519-523
Shielding | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Accelerators | doi.org/10.13182/NT09-A9236
Articles are hosted by Taylor and Francis Online.
Radiation shielding calculations were performed for the shielding design around beam injection and beam extraction areas at the 3-GeV proton synchrotron in the Japan Proton Accelerator Research Complex (J-PARC) with the PHITS Monte Carlo code. Prompt dose rates outside the shields were obtained from calculated neutron energy spectra and flux-to-dose conversion coefficients prepared for the shielding design in J-PARC. The thicknesses of shields were determined from the comparison results of the prompt dose rates with the criteria of dose limit for the design in J-PARC.
