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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Westinghouse’s lunar microreactor concept gets a contract for continued R&D
Westinghouse Electric Company announced last week that NASA and the Department of Energy have awarded the company a contract to continue developing a lunar microreactor concept for the Fission Surface Power (FSP) project.
Sanjeev Kumar Sharma, Manoj Kansal, N. Mohan, P. K. Malhotra, S. G. Ghadge
Nuclear Science and Engineering | Volume 169 | Number 2 | October 2011 | Pages 222-227
Technical Paper | doi.org/10.13182/NSE09-16
Articles are hosted by Taylor and Francis Online.
One of the important issues in severe reactor accident scenarios is the containment integrity and the characteristics of the source term that governs the ultimate radioactive releases to the environment. The releases are in the form of aerosols that are generated by the condensation of volatile fission products released from fuel, within the containment, during the severe accident. A loss-of-coolant accident with simultaneous failure of the emergency core cooling system has been postulated for a study of such aerosols. For the aerosol behavior in the containment, various removal mechanisms, such as gravitational settling, diffusional plate-out, and diffusiophoresis, and growth processes such as agglomerations and condensation have been included. The transport process such as leakage from the containment has also been modeled. This paper discusses the results of the studies carried out to estimate aerosols' behavior in the Tarapor Atomic Power Station (TAPS)-3&4 containment following their release during the postulated accident condition. It was found that the gravitational settling is the major aerosol removal mechanism following the postulated severe accident.