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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.
Do Heon Kim, Hyeong Ill Kim, Choong-Sup Gil, Young-Ouk Lee
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 274-278
Neutron Data | 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 Measurements and Instrumentation | doi.org/10.13182/NT09-A9194
Articles are hosted by Taylor and Francis Online.
New neutron production cross sections of tungsten isotopes such as 182W, 183W, 184W, and 186W have been validated through shielding benchmarks and criticality safety benchmarks with the MCNPX-2.5.0 code. The calculation results based on the new evaluations have been compared with those based on ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, and FENDL-2.1 as well as the benchmark experiments. In this paper, some noticeable improvements in calculations of the neutron leakage spectra from tungsten shields and the keff's for critical assemblies with tungsten are presented.
