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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
Former NRC commissioners lend support to efforts to eliminate mandatory hearings
A group of nine former nuclear regulatory commissioners sent a letter Wednesday to the current Nuclear Regulatory Commission members lending support to efforts to get rid of mandatory hearings in the licensing process, which should speed up the process by three to six months and save millions of dollars.
Marcel Reginatto, Eike Hohmann, Burkhard Wiegel
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 328-332
Neutron Measurements | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9203
Articles are hosted by Taylor and Francis Online.
Extended-range Bonner sphere spectrometers are well suited for spectrometry in neutron fields that extend from thermal energies to a few hundred mega-electron-volts. The data analysis, however, is not straightforward, and it is of interest to evaluate how well the main features of the spectrum can be determined by the measurements and to estimate the uncertainties of integral quantities of interest, e.g., fluence and dose. In this paper, we apply Bayesian parameter estimation to this problem. We use simulated data that model measurements made in neutron fields behind shielding at high-energy accelerators.