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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 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
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
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.