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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
Seyed Mohsen Hoseyni, Mohammad Pourgol-Mohammad
Nuclear Technology | Volume 193 | Number 3 | March 2016 | Pages 341-363
Technical Paper | doi.org/10.13182/NT15-47
Articles are hosted by Taylor and Francis Online.
The influence of model uncertainty is most pronounced in areas of limited knowledge and large uncertainties like severe accident (SA) calculations. Lack of a systematic methodology for this purpose makes this assessment difficult. This paper describes the treatment of model uncertainty in SA analysis for nuclear power plants, which is an area that has had limited past research. This paper aims at a systematic subject assessment. By review of available approaches, a methodology is structured to deal with alternative modeling options in SA code structure. The proposed methodology comprises three phases: the probability of each model is estimated (phase 1), the input uncertainty is quantified (phase 2), and the Bayesian model averaging technique is utilized to integrate the calculations of alternative models into the SA code (phase 3). Through this process, the degree of belief is quantified for the performance of alternative code models. The methodology evaluates available information and data from experiments and code predictions. The application of the proposed methodology is demonstrated on fission product release models for the LP-FP-2 SA experiment of the LOFT (Loss-of-Fluid Test) facility.