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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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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.”
Gerardo Martinez-Guridi, Pranab Samanta, Tsong-Lun Chu, Ji-Wu Yang
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 297-318
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3118
Articles are hosted by Taylor and Francis Online.
Following a loss-of-coolant accident (LOCA) in a nuclear power plant (NPP), the loss of electric-power generation, as might be precipitated by the unit tripping, may cause switchyard- and grid-instability with a subsequent loss-of-off-site power (LOOP). The LOOP usually is delayed by a few seconds or longer. This accident is called a LOCA with consequential LOOP, or a LOCA with delayed LOOP (abbreviated as LOCA/LOOP). NPPs are designed to cope with simultaneous LOCA and LOOP. The U.S. Nuclear Regulatory Commission (NRC) identified this issue as generic safety issue (GSI) 171, "Engineered Safety Feature Failure from a Loss-Of-Off-Site Power Subsequent to a Loss-of-Coolant Accident." NRC subsequently dropped GSI-171 and considers it resolved. We present the probabilistic risk analysis of the LOCA/LOOP scenario that was conducted as part of NRC's resolution of GSI-171. We analyze and quantify the core damage frequency (CDF) associated with this accident. Event/fault trees are developed covering the progression of the accident to core damage. We used engineering evaluations and judgments to estimate probabilities for the conditions identified in a LOCA/LOOP scenario and to obtain a bounding evaluation of the CDF. We show that the contribution of such an accident to CDF depends on electrical-load sequencing and shedding capabilities; plants with adequate capabilities incur a minimal additional contribution to risk. No single plant design is known to be vulnerable to all the conditions; only some of the conditions may apply to some plants.