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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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.”
Cheol Woo Lee, Young-Ouk Lee, Young-Sik Cho
Nuclear Technology | Volume 168 | Number 1 | October 2009 | Pages 144-148
Dose/Dose Rate | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 1) / Dosimetry | doi.org/10.13182/NT09-A9115
Articles are hosted by Taylor and Francis Online.
Evaluation of the skyshine dose for the proton linac facility of the Proton Engineering Frontier Project in Korea was performed in this study. To predict the skyshine dose level outside of the facility, a Monte Carlo method (MCNPX code), analytical method using an estimation formula, and SKYSHINE-KSU codes using an integral line-beam method were considered in the evaluations. The neutron spectrum at the outer surface of the roof of the facility was considered as the radiation source term. The results from each method were in good agreement for the distance from 200 to 1000 m. The neutron dose of 1.65 × 10-4 Sv/h is expected at the fence of the facility, which is 400 m from the accelerator room.