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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
M. Srinivasan, K. Subba Rao, S. B. Garg, G. V. Acharya
Nuclear Science and Engineering | Volume 102 | Number 3 | July 1989 | Pages 295-309
Technical Paper | doi.org/10.13182/NSE89-A27479
Articles are hosted by Taylor and Francis Online.
A number of interesting systematics and correlations have been deduced by analyzing the criticality data of special actinide nuclides using concepts embodied in the Trombay criticality formula (TCF). The k∞ of fast metal actinide nuclides gives a remarkable linear correlation with the fissility parameter Z2/A. The neutron leakage probability of all fast metal cores characterized using a constant parameter σstd enables computation of the critical mass value of any unknown fissile nuclide knowing only its Z2/A value. Since the neutron leakage probability from dilute fissile solutions is primarily governed by the scattering/slowing down properties of the hydrogen present in water, critical masses and subcritical limits can be predicted for any water-reflected system at any specified hydrogen-to-actinide atomic ratio knowing only the k∞ value of the given fissile solution. In the case of fast fissible actinide systems, the neutron leakage probability can be characterized by a single parameter σstd, but having a slightly different value from that of fast fissile systems. Due to their fission thresholds, however, attempts to deduce any systematics in their k∞ values have not been very successful. The importance of compiling not only critical radius/mass data but also k∞, the critical surface mass density , the degree of reflection parameter Y, etc., has been clarified while preparing criticality data tabulations for ready reference. These quantities can be used along with the TCF to compute core dimensions and fissile inventories required to yield any specified safe subcritical keff value.
