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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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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.”
Husam Gurol, Ali E. Dabiri
Fusion Science and Technology | Volume 6 | Number 3 | November 1984 | Pages 605-615
Technical Paper | Safety/Environmental Aspect | doi.org/10.13182/FST84-A23142
Articles are hosted by Taylor and Francis Online.
The safety of the Mirror Advanced Reactor Study (MARS) tandem mirror reactor is assessed. Only prompt consequences to the public at the plant boundary, which is taken to be 1000 m, are considered. The major radioactive inventories in MARS reside in the first-wall/blanket structure, coolant, and tritium. The greatest radioactivity resides in the HT-9 first-wall/blanket structure. The only accident scenario identified that could lead to a first-wall meltdown was a loss-of-coolant accident (LOCA) accompanied by the inability to shut off the plasma. However, since only oxides of molybdenum are expected to be volatized from the hot HT-9 structure, the public consequences are found to be low. A LOCA can result in large doses if the activity in the activated corrosion products and LiPb coolant can be transported outside the reactor containment building. However, most of the LiPb would be expected to solidify, and any aerosols that are produced will likely plate out on surfaces or settle. Various tritium accident scenarios were considered. Release of all the tritium in the reactor building (51 g) leads to a dose of 21 rem. A much more likely accident involves partial leakage due to some reactor containment damage.