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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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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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Nuclear new build procurement considerations
It may seem counterintuitive, but the best time to enhance the ability to support operations and maintenance for a new plant is before construction starts. This is one of many lessons learned by the currently operating nuclear fleet. As construction and startup of many nuclear facilities was completed, it quickly became evident that the ability to efficiently support operations and maintenance was limited. Most of the information necessary to establish and manage procurement of spare and replacement items, maintenance, and configuration of the facilities was unavailable and had to be gathered on a case-by-case, “on-demand” basis. Absence of necessary information and the associated challenges resulted in the need for staff augmentation and multiyear-long projects to develop equipment bills of material and maintenance programs and to perform technical evaluations for the huge quantities of spare and replacement items being requested.
Kohtaro Ueki, Yuichi Ogawa, Hiroshi Naito, Tomonori Hyodo
Fusion Science and Technology | Volume 7 | Number 1 | January 1985 | Pages 90-98
Technical Paper | Shielding | doi.org/10.13182/FST85-A24521
Articles are hosted by Taylor and Francis Online.
A 14-MeV neutron streaming through a narrow vertical hole duct in the diagnostics room of a Deuterium-Tritium Fusion Experimental Device (R tokamak) was analyzed using the Monte Carlo coupling technique. Neutron dose rate distributions in the horizontal direction as well as in the axial direction along the vertical hole duct were calculated to evaluate the neutron streaming effect through the hole duct. The dose rate distribution in the axial direction undergoes relatively small changes, but the distribution changed abruptly in the horizontal direction. Compared to ANISN results, Monte Carlo calculations show a neutron streaming effect at locations beyond the vertical hole duct axis in the horizontal direction. The fractional standard deviation (FSD) due to error propagation was calculated by the ORION code based on an error propagation equation. The FSDs were within 0.06 at the detector locations along the axial direction along the vertical hole duct; but, they were as much as 0.25 to 0.47 for >15 cm beyond the hole duct axis in the horizontal direction.