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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Qingmin Zhang, Zhigang Hu, Bangjie Deng, Mengxuan Xu, Yuhang Guo
Nuclear Science and Engineering | Volume 186 | Number 3 | June 2017 | Pages 293-302
Technical Paper | doi.org/10.1080/00295639.2016.1273619
Articles are hosted by Taylor and Francis Online.
The self-powered neutron detector (SPND) is popularly used as an in-core neutron flux monitor in reactors due to its simple structure, self-powered feature. However, its response delay needs compensation to obtain the actual real-time neutron flux for reactor control and protection. In this paper, a simple iterative method for compensating SPND response delay is proposed as well as noise filtering. Two favorable noise filtering methods were compared, and then, the moving average filter was chosen. The governing differential equations were established according to decay mechanism, and then, iterative compensation relations for delay compensation were established by discretization with simplicity and flexibility. The test result shows that the compensated response delay for a prompt jump of neutron flux is only 0.9 s, indicating its effectiveness. Furthermore, the dependence on initial conditions and sampling time interval was also studied, indicating that two initial condition determination modes for two typical detector start-up situations can be chosen correspondingly for delay minimization and critical sampling with a time interval of about 0.7 s, which shows consistency with the Von Neumann stability analysis. Finally, our method has been compared with the Z-transform method and verified with measured current, which showed its better performance.