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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
Jinho Song, Changwook Huh, Namduk Suh
Nuclear Technology | Volume 178 | Number 3 | June 2012 | Pages 258-266
Technical Paper | Reactor Safety | doi.org/10.13182/NT12-A13592
Articles are hosted by Taylor and Francis Online.
Weaknesses of the current Severe Accident Management Guideline (SAMG) in handling the cooling of a molten core are discussed, and three improvements for the SAMG are presented. It is suggested that instrumentation to detect either a breach of the reactor vessel or a discharge of corium into the reactor cavity is essential to effectively perform the SAMG. A detailed analysis for a specific plant is necessary to make a decision as to whether preflooding or postflooding should be initiated for effective molten core cooling. Also, an optimal choice of depressurization capacity not only would significantly delay failure of the reactor vessel but also would increase the coolability margin of the molten corium in a reactor cavity. Analyses using the MELCOR computer code were performed for the Ulchin Units 1 and 2 and Kori Unit 1 nuclear power plants to illustrate the effectiveness of the proposed improvements in cooling of the molten core in the reactor cavity, where in-vessel retention of molten corium by preflooding is not feasible.