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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
DOE-EM finishes cleanup of legacy Oak Ridge reactor lab site
The Department of Energy’s Office of Environmental Management announced that the 30-foot-long, 37,600-pound reactor vessel from Oak Ridge National Laboratory’s Low Intensity Test Reactor was shipped to EnergySolutions’ low-level radioactive waste facility in Clive, Utah, in late April.
W. James Boatwright, David W. Hiltbrand, Whee G. Choe
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 289-294
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2840
Articles are hosted by Taylor and Francis Online.
TU Electric has developed and obtained U.S. Nuclear Regulatory Commission (NRC) approval of the methodologies required to support core reload safety analyses. The Electric Power Research Institute-sponsored computer codes RETRAN-02 and VIPRE-01 are used in the non-loss-of-coolant-accident thermal-hydraulic analyses. These methods were employed to support the loading of the core of the Comanche Peak Steam Electric Station, Unit 1 (CPSES-1), Cycle 5.An overview of the reload safety analysis development effort is provided, with the focus on the qualification of the system transient analysis methodologies. Interactions with the NRC are described. Included is a discussion of the types of questions asked by the NRC and the corresponding TU Electric responses. Comparisons of calculated results to actual plant data which demonstrate the validity of the CPSES plant model, are provided. The importance of performing "good" benchmark comparisons is addressed as it relates to the demonstration of technical competence in the use and interpretation of RETRAN.The effectiveness of the approach used by TU Electric to obtain NRC approval of the reload safety analysis methodology is examined in retrospect. Finally, an assessment is made of the benefits, tangible and intangible, derived from having an in-house reload safety analysis capability.