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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
N. N. Ponomarev-Stepnoi, V. G. Bubelev, Ye. S. Glushkov, G. V. Kompaniets, V. I. Nosov
Nuclear Science and Engineering | Volume 119 | Number 2 | February 1995 | Pages 108-115
Technical Paper | doi.org/10.13182/NSE95-A24075
Articles are hosted by Taylor and Francis Online.
The hydrogen content of zirconium hydride blocks used as the moderator in Topaz-2-type space reactors is estimated according to correlation-regression analysis procedures of mathematical statistics and is based on the results of the definition of the reactivity of the blocks in a research critical assembly. A linear mathematical model for a variable response is formulated within the framework of the first-order perturbation theory applied to the estimation of reactivity effects in reactors. A PASPORT computer code is written based on the developed algorithm. The statistical analysis of the available data performed by using PASPORT shows that the developed approach allows determination of the insignificance of the contribution of the impurities to the reactivity of the blocks, verification of the manufacturer’s data on the hydrogen content in zirconium hydride blocks, and estimation of the reactivity shift in a standard block.
