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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Keiichi Saito
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 467-474
Technical Paper | doi.org/10.13182/NSE72-A22514
Articles are hosted by Taylor and Francis Online.
Lehto and Carpenter performed a set of experiments concerning the temperature and the gamma-ray fluctuations in a relatively low power reactor with high fission product inventories. The results are uniformly and quantitatively analyzed by applying the theoretical approach previously developed by the present author. The new features of the present consideration are the following two points: (a) incorporation of the external noise source in the previous theory which includes only the inherent noise source theoretically determined with the use of the first-order linearized Markoffian model of the reactor noise phenomenon; (b) analysis of the cross power spectral density (CPSD) between the two state quantities characterizing the core performances. The first point gives a successful interpretation of most of the experimental results in spite of adopting a simple analytical model. The newly extended framework of the theory can include also a reactivity transfer-function analysis with the use of a proper driving function. The phase of the CPSD between the power and the temperature is calculated on a one-space-point, a one-delayed-group, and a one- or two-feedback-loop reactor model. The results suggest that the experimental determination of the phase will provide both a check point for the theoretical model of the dynamical behaviors of at-power reactors and some bits of information on the feedback parameters.