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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
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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
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.
