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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
S. Ohira, E. Tada, K. Hada, Y. Neyatani, T. Maruo, M. Hashimoto, T. Araki, K. Nomoto, D. Tsuru, T. Ishida, Y. Goto, T. Tsunematsu
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 642-646
Safety and Safety System | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22666
Articles are hosted by Taylor and Francis Online.
In Japan, Fundamental approach for ensuring safety of the ITER plant was established by the Technical Advisory Committee for the Reactor Regulation Division of Science and Technology Agency of Japan in 2000. The approach settled the basic safety principles and approaches as the technical requirements on safety design and assessment derived from the safety characteristics of the ITER plant It was concluded that prevention of accidents can be achieved sufficiently by means of ensuring and maintaining the structural integrity of the enclosures containing radioactive materials against anticipated loads during operation, and low hazard potential of radioactive materials contained can be maintained within prescribed limits sufficiently by the vented detritiation/filtering clean-up system (confinement system) even if large release is postulated. For embodiment of the safety design concepts to the ITER tritium facility, some practical considerations should be taken for the tritium containment barriers, e.g., limitation of tritium permeation and leak, provision of an appropriate ventilation/detritiation system for maintenance, those to ensure the mechanical integrity etc.