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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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
R. C. Sanders, G. E. Mueller
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 289-296
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32182
Articles are hosted by Taylor and Francis Online.
The maximum credible accident for which a nuclear reactor must be analyzed is a loss-of-coolant accident (LOCA) due to a major rupture in the primary system. Such an accident has been analyzed for a conceptual design of a consolidated nuclear steam system (CNSS) using the thermal-hydraulic computer code RELAP4/MOD5. The results of the analysis show that the maximum fuel cladding temperature during the accident is ∼344°C (652°F), which is sufficiently low to preclude any damage to the reactor core. Based on the results of this analysis, it appears that a LOCA in a CNSS may be less severe than in typical loop-type pressurized water and boiling water reactors. This result is expected because of the smaller piping connected to the CNSS reactor vessel