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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.”
K. V. Subbaiah, C. Sunil Sunny
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 265-272
Technical Paper | Radiation Protection | doi.org/10.13182/NT01-A3221
Articles are hosted by Taylor and Francis Online.
KAMINI is the Kalpakkam Mini Reactor, and its main purpose is to cater to experimental needs and for neutron radiography. It is a water-cooled reactor with 233U as the fissile material. Using the Monte Carlo n-particle transport code MCNP, shielding optimization calculations are carried out for the south beam port tube, which is meant for neutron radiography of spent-fuel subassemblies of the fast breeder test reactor. The neutron beam port is a graded cylindrical aluminium channel starting from the center of the reactor core; it pierces through the biological shield and is 2 m long. The diameter of the channel at the core center is 54 mm, at the other end it is 25 cm, and it is 0.5 m below the floor level. The latter end serves as the neutron surface source for these calculations. The calculations have been carried out in cylindrical geometry (r,z) of shield structures. From results of the analysis, a movable shield 50 cm thick (25 cm paraffin and 25 cm lead), 75 cm wide, and 172 cm long extending ~95 cm into the demineralizer room (cooling water purification room) is proposed to replace the existing temporary shield structure. In addition, fixed shields of the same thickness and width of 50 cm on either side of the beam is recommended to reduce the dose levels to a few tens of microsieverts per hour in the accessible areas. Further, the lead-shielded cylindrical tube meant for insertion of irradiated fuel subassemblies for neutron radiography needs to be covered with 20 cm of paraffin up to a height of 1 m from ground level to avoid streaming of neutrons through the air column.