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The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
D. H. Zhu, J. L. Chen, Z. J. Zhou, R. Yan, R. Ding
Fusion Science and Technology | Volume 66 | Number 2 | October 2014 | Pages 337-342
Technical Paper | doi.org/10.13182/FST13-738
Articles are hosted by Taylor and Francis Online.
To investigate the influences of dispersed lanthanum oxide (La2O3) additive on the properties of a tungsten (W)-based plasma-facing material, ultrafine-grained W-1% La2O3 composite has been successfully fabricated using the resistance sintering under ultrahigh pressure method, which can suppress W grain growth during sintering processes. Its relative density, Vickers microhardness, microstructure, and thermal conductivity have been analyzed and compared with those of pure W. Moreover, its behaviors under fusion-related conditions, i.e., edge plasma loading in the HT-7 tokamak and transient heat flux simulated by a high-intensity pulsed ion beam, have been evaluated. It is shown that without the fine-grain strengthening effect of dispersed particles, the La2O3 additive as second-phase particles being dispersed in W-based plasma-facing material degrades the material resistance ability under plasma heat loading.
