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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.
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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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Shashi Kant Verma, S. L. Sinha, D. K. Chandraker
Nuclear Science and Engineering | Volume 190 | Number 2 | May 2018 | Pages 195-208
Technical Paper | doi.org/10.1080/00295639.2017.1413874
Articles are hosted by Taylor and Francis Online.
The objective of the present work is to establish the effect of spacer and geometrical parameters of nuclear fuel rods on the turbulent mixing rate in subchannels of the advanced heavy water reactor (AHWR) rod bundle. Experiments on the AHWR rod bundle have been carried out in a scaled test facility developed at Bhabha Atomic Research Centre, Trombay, Maharashtra. In order to confirm the validity of the proposed method, experimental data on the turbulent mixing rate were obtained using a tracer technique under adiabatic conditions with 3.5-m vertical test channels, consisting of three subchannels. The spacer was installed at 2963 mm (37 mm at the end of the mixing section), 2926 mm (74 mm at the end of the mixing section), and 2889 mm (111 mm at the end of the mixing section) from the entry section in the test section, respectively, for three different positions. The experimental results (blockage ratio 4%) have been compared with the case without spacer and finally new correlations have been developed between average mixing number, combined Reynolds number, and gap-to-centroidal ratio (S/δ). The range of average Reynolds number covered was 0 to 6424. The correlation is applicable for a vertical pressure tube–type boiling water reactor (AHWR) with a reasonable accuracy. The instrument was calibrated prior to each set of analyses with standard solution. It predicts a reasonable mixing at a higher S/δ as compared to without spacer, which is the most improved feature of the correlation when compared with the existing ones. The uncertainty analysis has been carried out for the measurement of flow rate, concentration, and height of the test section. The proposed correlation may be applicable for the thermal-hydraulic design of an AHWR with an improved accuracy. A complete set of mixing data was obtained which can be used to calibrate thermal-hydraulic codes.