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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.
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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Takeshi Matsuoka, Michiyuki Kobayashi, Kazuo Takemura
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 285-295
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34212
Articles are hosted by Taylor and Francis Online.
A reliability analysis using the GO-FLOW methodology is given for the emergency core cooling system (ECCS) of a marine reactor experiencing either a collision or a grounding accident. The analysis is an example of a phased mission problem, and the system is a relatively large system with 90 components. An overview of the GO-FLOW methodology, a description of the ECCS, and the analysis procedure are given. Time-dependent mission unreliabilities under three accident conditions are obtained by one GOFLOW chart with one computer run. The GO-FLOW methodology has proved to be a useful tool for probabilistic safety assessments of actual systems.