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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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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.”
Michelle Pitts, Farzad Rahnema, Tom G. Williamson, Fitz Trumble
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 1-18
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2847
Articles are hosted by Taylor and Francis Online.
Hundreds of criticality experiments were performed at Oak Ridge National Laboratory in the 1950s. Several sets of these experiments were used to determine the critical properties of 233U and 235U. Here, four sets are analyzed to provide benchmark descriptions for validation of computational tools used by nuclear criticality specialists. All four sets were performed in water-reflected spherical geometry and contained a highly enriched uranyl fluoride solution (93.18% 235U) with the hydrogen-to-fissile ratio of measurements ranging from 35.8 to 1272. The scope of these experiments spans the minimum values of the subcritical mass limit curve. One experiment was never reported in the open literature, and three experiments were performed at elevated temperatures. An uncertainty in the experimental keff was found by sensitivity studies on reported measurement uncertainties, inconsistencies, and omissions in experimental parameters. To be useful for all computer codes, one-dimensional benchmark configurations were determined for all sets of experiments. The descriptions can be used to find bias values for a code/cross-section package. The keff values for similar configurations can then be corrected using the bias values. The sensitivity analysis of the experiments was performed using ONEDANT with 27-group ENDF/B-IV cross sections and MCNP with continuous-energy ENDF/B-V cross-section data. The keff values for both one- and three-dimensional configurations were found using MCNP with ENDF/B-V and ENDF/B-VI cross-section data. The values for keff for the one-dimensional configuration were also found by using ONEDANT and KENO V.a with Hansen-Roach and 27-group ENDF/B-IV cross sections.