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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
M. Z. Youssef, Y. Watanabe, A. Kumar, Y. Oyama, K. Kosako
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1843-1852
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29612
Articles are hosted by Taylor and Francis Online.
Performing integral experiments with a 14 MeV line source offers better simulation to the neutron source conditions (in terms of energy and angular distribution) of the toroidal plasmas in Tokamaks. Because of the linearity of the neutron transport equation, a line source can be simulated by superimposing results from many point sources aligned on one line, provided the number of these point sources is large. The simulation was experimentally realized at the FNS facility within the USDOE/JAERI Collaborative Program on Fusion Neutronics. In this paper, the theoretical aspects of a line source simulation are discussed. Specifically, analytical results for achieving this simulation by continuously moving a point source of speed V within a distance of length 2L; [continuous operation (CO.) mode] are compared to results obtained from several point sources located at discrete number of locations within the distance 2L [stepwise operation (S.O.) mode]. In the C.O. mode it was shown that for activation measurements, ideal simulation to a line source of length 2L with a point source moving at speed V could be achieved, provided the decay constant λ of the activated product satisfies the condition λ.(2L/V) << 1. In the S.O. mode, the number of point source locations, the distance from the simulated line source where the neutron radiation effects are measured, and the type of reactions (threshold vs. non-threshold) considered are important factors in determining the degree of simulation. For example, it was shown that better simulation can be achieved if the source locations are chosen to be at points that are directly related to the roots xi's of the Gauss-Legendre set PN(xi)=0, where N is the number of source locations. It was shown that larger number of point sources are needed to reproduce the line source effects on threshold-type reactions [e.g. 7Li(n,n'α)t] than on non-threshold reactions [e.g. 6Li(n,α)t]. Several transport calculations were also performed to study the degree of simulation from multiple point sources on the characteristics of the test assembly used in Phase IIIA of the program. In particular, the anisotropy of the incident neutron source arising from the structure of the target assembly, coolant channel, and water coolant was studied and compared to the case of isotropic point sources. It was shown that using N ≥ 20 points is adequate to the analysis of Phase III.A experiments.