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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
BWXT announces nuclear manufacturing plant expansion
BWX Technologies announced today plans to expand and add advanced manufacturing equipment to its manufacturing plant in Cambridge, Ontario, Canada.
A $36.3 million USD ($50M CAD) expansion will increase the plant’s size by 25 percent—to 280,000 square feet—and another $21.7 million USD ($30M CAD) will be spent on new equipment to increase and accelerate its output of large nuclear components. The investment will increase capacity and create more than 200 long-term jobs for skilled workers, engineers, and support staff, according to the company.
Susan Hogle, Charles W. Alexander, Jonathan D. Burns, Julie G. Ezold, G. Ivan Maldonado
Nuclear Science and Engineering | Volume 185 | Number 3 | March 2017 | Pages 473-483
Technical Paper | doi.org/10.1080/00295639.2016.1272973
Articles are hosted by Taylor and Francis Online.
This work applies to recent initiatives at the Radiochemical Engineering Development Center at Oak Ridge National Laboratory to optimize the production of transcurium isotopes in the High Flux Isotope Reactor in such a way as to prolong the use of high-quality heavy curium feedstock. By studying the sensitivity of fission and transmutation reaction rates to the neutron flux energy spectrum, a flux filtering methodology is explored for increasing the fraction of (n,γ) reactions per neutron absorption. Filter materials that preferentially absorb neutrons at energies considered detrimental to optimal transcurium production are identified, and transmutation rates are examined with high-energy resolution. Experimental capsules are irradiated employing filter materials, and the resulting fission and activation products are studied to validate the filtering methodology. Improvement is seen in the production efficiency of heavier curium isotopes in 244Cm and 245Cm targets and potentially in the production of 252Cf from mixed californium targets. Further analysis is recommended to evaluate longer-duration irradiations more representative of typical transcurium production.