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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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Nuclear Science and Engineering
Fusion Science and Technology
Ensuring a role for nuclear in the response to climate change
Nuclear power is an important tool in the response to climate change, and advanced reactors may offer advantages over existing plants in providing carbon-free generation at the scale necessary to respond to the existential challenge that climate change presents. The International Atomic Energy Agency is aggressively addressing issues related to the possible transition to advanced reactors. This letter is to urge a redoubling of effort by Member States to put in place the necessary capabilities to deal with the challenges that they present.
Vinay Kumar, Lalit Singh, A. K. Tripathi
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 20-28
Technical Paper | dx.doi.org/10.13182/NT16-89
Articles are hosted by Taylor and Francis Online.
Any risk in safety-critical or control applications may lead to catastrophic disaster; hence, safety is a primary concern for such applications. The impact of risk varies from minor inconvenience and cost to personal injury, significant economic loss, and death. Therefore, a safety assessment process should be an inherent part of the system development process to make a system safe or to ensure that the effects from failures are minimized. This paper deals with a new probabilistic approach to quantify the safety of safety-critical systems (SCSs) and control systems based on probabilistic safety assessment to deal with the shortcomings of the existing techniques. The methodology has been tested on 29 operational data sets to validate its effectiveness. This paper demonstrates the methodology on the digital feedwater controller system of a nuclear power plant. The results indicate that the method can identify possible hazards and quantify such hazards of a SCS.