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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
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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Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
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.”
Nick DeJulia, Trevor Jones (AMS)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1251-1259
A pressurized water reactor (PWR) is equipped with a magnetically coupled positioning system known as a control rod drive mechanism (CRDM). In many cases, the plant system that measures the position of the control rods in the reactor core is the digital rod position indication (DRPI) system. The DRPI system is designed to continuously sense and display the positions of each of the control and shutdown rods. Both of these systems consist of coils above the reactor head, connectors at the reactor head and at the containment penetration, instrumentation and power cabinets, and long runs of interconnecting cables in between these system components. The objective of cable testing is to evaluate the condition of the rod control and position indication coils, connections, cables and to identify any defects or anomalies that may adversely affect their normal operation. Various electrical measurements can provide insight into the health and reliability of these rod control and rod position cable circuits. Some measurements are used to identify configuration anomalies, others test the integrity of connectors and proper isolation from station ground, and some validate the health of the coil to identify resistive connections, insulation degradation, or turn-to-turn shorts. This systematic approach to rod control and rod position coil and cable testing increases system reliability, reduces the likelihood of unplanned outages from dropped rods, and reduces outage times and maintenance costs which in turn reduces costs for the electrical utility.