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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Steven E. Skutnik, Man-Sung Yim
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 374-381
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14169
Articles are hosted by Taylor and Francis Online.
The effect of simplifications in nuclear fuel depletion analysis as well as the effect of cross-section uncertainties were evaluated as to their impact upon material attractiveness for weapons diversion purposes. The effect of simplified depletion models for material attractiveness evaluation was evaluated through a comparison of pressurized water reactor fuel for several benchmark cases, using experimentally measured values along with a two-dimensional lattice physics model (TRITON) and a point depletion model (ORIGEN-S). Simplifications such as the use of the ORIGEN-S depletion libraries and assumptions of homogeneous core enrichment were found to have a negligible impact on material attractiveness evaluation, particularly relative to uncertainties in experimental measurements; additionally, simplified irradiation power histories do not introduce unacceptable errors into the attractiveness evaluation. Finally, the overall sensitivity of material attractiveness and associated uncertainty was found to be greater for transuranic mixtures compared to plutonium as a function of both burnup and decay time; however, associated uncertainties are generally small and not prohibitive to material attractiveness discrimination. As a result, the use of simplified depletion models such as ORIGEN-S appears to be well justified for use in material attractiveness evaluation for proliferation resistance studies.