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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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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, M. A. Abdou, A. Kumar, Li Zhang, K. Kosako, Y. Oyama, F. Maekawa, Y. Ikeda, C. Konno, H. Maekawa
Fusion Science and Technology | Volume 28 | Number 2 | September 1995 | Pages 320-346
Technical Paper | Fusion Neutronics Integral Experiments — Part II / Blanket Engineering | doi.org/10.13182/FST95-A30649
Articles are hosted by Taylor and Francis Online.
Experimental simulation to a line source has been realized at the Japan Atomic Energy Research Institute (JAERI) Fusion Neutronics Source within the U.S. Department of Energy/JAERI collaborative program on fusion neutronics. This simulation, achieved by cyclic movement of an annular Li2O test assembly relative to a stationary point source, was a step forward in better simulation of the energy and angular distributions of the incident neutron source found in tokamak plasmas. Thus, compared with other experiments previously performed with a stationary point source, the uncertainties (that are system dependent) in calculating important neutronics parameters, such as tritium production rate (TPR), will be more representative of those anticipated in a fusion reactor. The rectangular annular assembly used is 1.3 × 1.3 m and 2.04 m long with a square cavity of 0.42 × 0.42 m cross section where the simulated line source (2 m long) is located axially at the center. To characterize the incident neutron source, flux mapping with foil activation measurements was performed in the axial direction (Z = −100 cm to Z = 100 cm) at the front surface of the assembly in the cavity with the annular blanket in place, and comparison was made to the bare line-source case (without annular blanket). Three phases of experiments were performed. In Phase-IIIA, a 1.5-cm-thick stainless steel first wall was used. An additional 2.45-cm-thick carbon layer was added in Phase-IIIB, and a large opening (42.55 × 37.6 cm) was made at one side at the center of the annular assembly in Phase-IIIC. Calculations were performed independently by the United States and JAERI for many measured items that included TPR from 6Li(T6), 7Li(T7), in-system spectrum measurements, and various activation measurements. In this paper, the calculated-to-measured values for the aforementioned measured items are given, as obtained separately by the United States and JAERI. In addition, the mean value of the prediction uncertainties of the local and line-integrated TPR and the associated standard deviations are given based on the calculational and experimental results obtained in all the experiments.