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IAEA, PNNL test new uranium enrichment monitor
A uranium enrichment monitor developed by a team at Pacific Northwest National Laboratory will soon be undergoing testing for nonproliferation applications at the International Atomic Energy Agency Centre of Excellence for Safeguards and Non-Proliferation in the United Kingdom. A recent PNNL news article describes how the research team, led by nuclear physicist James Ely, who works within the lab’s National Security Directorate, developed the UF6 gas enrichment sensor (UGES) prototype for treaty verification and other purposes.
Qiang Huang, Jin Jiang
Nuclear Technology | Volume 207 | Number 5 | May 2021 | Pages 711-725
Technical Paper | doi.org/10.1080/00295450.2020.1794436
Articles are hosted by Taylor and Francis Online.
One of the most important considerations in the design of electronic systems for post-accident monitoring in a nuclear power plant is how to deal with the complex and uncertain radiation environments. Without using special design methodologies and adequate protection, nonradiation-hardened commercial-off-the-shelf (COTS) electronic components can easily be damaged. In this paper, a new design methodology is proposed so that COTS components can be used in building post-accident monitoring systems (PAMSs). To validate the effectiveness of the methodology, a prototype wireless post-accident monitoring system has been designed, implemented, and evaluated in a 60Co gamma radiation environment. It has been concluded that even at a dose rate of 20 krad (Si)/h, the prototype system operates satisfactorily even after being irradiated for 21 h. The system also operates satisfactorily at a low dose rate of 200 rad (Si)/h. It can be concluded that, even with COTS components, the proposed design can effectively extend the lifespan of post-accident monitoring systems in different radiation environments. Based on the experimental results, it can be said with confidence that the developed radiation-tolerant wireless monitoring system can operate for at least 8 h under the highest observed dose rate (530 Sv/h) encountered during the Fukushima Daiichi nuclear disaster and would have been able to provide crucial information to first responders following the accident.