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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Jeng-Ning Wang, Chung-Hsin Lu, Kuo-Wei Lee, Uei-Tyng Lin, Shiang-Huei Jiang
Nuclear Technology | Volume 168 | Number 1 | October 2009 | Pages 101-107
Dose/Dose Rate | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 1) / Radiation Protection | doi.org/10.13182/NT09-A9107
Articles are hosted by Taylor and Francis Online.
The site dose rate of a spent-fuel storage facility to the populace is a major concern in a radiation protection project. Shielding analysis of the facility must be performed to ensure that the nearby dose rates are within regulation limitations. The purpose of this study was to simulate an independent spent-fuel storage installation (ISFSI) storage facility with different methods and different conditions for validation and analysis. The discrete ordinates code DORT and the SKYSHINE III code were used for the cask surface flux estimation and the site dose rate calculation, respectively. The Monte Carlo code MCNP was also utilized to estimate the surface dose rate and site dose rate by its subsequent calculation. Various cask decay heats (23, 14, and 7 kW/cask) were considered as the source conditions. A facility layout composed of 30 casks was also simulated by the MCNP code and analyzed for the cask self-shielding effect to a certain detecting point. For a single storage cask, comparisons of the site dose rates calculated by different methods were carried out at variant distances. For the layout simulation, the calculated results indicated that the self-shielding effect could be roughly classified into several groups according to the location of the storage cask, and a factor could be assigned to each group. These classified factors might help to infer the site dose in variant layout designs. The site dose rates calculated by different codes were compared for the whole facility, too. In spite of the similar dose rates on the cask surface, the difference of site dose rates changes with decay heat. The layout study of the ISFSI facility could offer information to make the site dose estimation more efficient as many layout assessments are needed.