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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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
General Atomics tests fuel as space nuclear propulsion R&D powers on
General Atomics Electromagnetic Systems (GA-EMS) has announced that it has subjected nuclear thermal propulsion (NTP) fuel samples to several “high-impact” tests at NASA’s Marshall Space Flight Center (MSFC) in Huntsville, Ala. That news comes as NASA, the Department of Defense, the Department of Energy, and multiple nuclear and space technology companies continue to build on recent progress in nuclear thermal rocket design and demonstration.
R. N. Blomquist, E. M. Gelbard
Nuclear Science and Engineering | Volume 141 | Number 2 | June 2002 | Pages 85-100
Technical Paper | doi.org/10.13182/NSE01-30
Articles are hosted by Taylor and Francis Online.
We compare nominal efficiencies, i.e., variances in power shapes for equal running time, of different versions of the Monte Carlo (MC) eigenvalue computation. The two main methods considered here are "conventional" MC and the superhistory method. Within each of these major methods, different variants are available for the main steps of the basic MC algorithm. Thus, for example, different treatments of the fission process may vary in the extent to which they follow, in analog fashion, the details of real-world fission, or they may vary in details of the methods by which they choose next-generation source sites. In general the same options are available in both the superhistory method and conventional MC, but there seems not to have been much examination of the special properties of the two major methods and their minor variants. We find, first, that the superhistory method is just as efficient as conventional MC and, second, that use of different variants of the basic algorithms may, in special cases, have a surprisingly large effect on MC computational efficiency.