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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
Fumihiro Masukawa, Yoshihiro Nakane, Yosuke Iwamoto, Hiroshi Nakashima
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 680-684
Accelerators | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Nuclear Plant Operations and Control | doi.org/10.13182/NT09-A9289
Articles are hosted by Taylor and Francis Online.
The radioactivity produced in accelerator cooling water was estimated to determine the maintenance scenario of Japan Proton Accelerator Research Complex (J-PARC) accelerators. The PHITS and the MCNPX codes were used to calculate the proton and neutron fluxes in water-cooled accelerator components. The activation cross-section sets of oxygen for high-energy protons and neutrons were evaluated from the available experimental data and theoretically calculated data by the INC/GEM and the LAHET codes. The radioactivity from corrosion products was also estimated by scaling of the measurements at the High Energy Accelerator Research Organization 12 GeV Proton Synchrotron Experiment (KEK-PS) and Los Alamos Meson Physics Facility (LAMPF). The tritium estimation is an acceptable level for disposal to the environment, while short-lived nuclides at the 3-GeV synchrotron may raise the dose rate in the machine room.