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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Mohamed A. E. Abdel-Rahman, Mohamed A. E. M. Ali, Sayed A. El-Mongy
Nuclear Technology | Volume 206 | Number 5 | May 2020 | Pages 766-778
Technical Paper | doi.org/10.1080/00295450.2019.1697173
Articles are hosted by Taylor and Francis Online.
This research work aims to investigate the penetrability of electromagnetic gamma rays and fast neutrons and the static performance of newly developed concrete. To achieve this target, seven concrete samples of three different coarse aggregates—dolomite, hematite, iron slag (with five different densities, i.e., 3.23, 3.34, 3.42, 3.10, and 3.03 g/cm3, respectively) with dolomite used as the control specimen—have been synthesized and investigated to determine their mechanical and radiation penetration properties. The mechanical performances were evaluated in terms of tensile and compressive strength, slump measurements, and water permeability. X-ray fluorescence was carried out to determine the chemical composition of the synthesized materials. The materials’ mineralogical constituents were also determined by X-ray diffraction analysis. The radiation transmissioxn characteristics were also checked by using gamma-ray collimated beams of both 60Co and 238Pu/Be neutron source. A stilbene crystal organic scintillator coupled with a fast n/γ pulse shape discriminating spectrometer as well as an NaI(Tl) scintillator gamma spectrometer were used to measure the radiation penetrated through the concrete samples. The fast neutron macroscopic cross section and total gamma-ray linear attenuation were derived for the developed mixes. The results obtained show that iron slag concrete of density 3.10 ton/m3 has superior characteristics against the transmission of gamma rays and fast neutrons and distinguished resistance withstanding mechanical pressure and loads.