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Division Spotlight
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
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.
Sang Lung Chan
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 191-212
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3785
Articles are hosted by Taylor and Francis Online.
The U.S. Nuclear Regulatory Commission (NRC) is consolidating all its severe-accident codes into one code, MELCOR, and making an effort to bring it into a state of parity with SCDAP/RELAP5/MOD3.3 (S/R5/M3.3) to model a Three Mile Island Unit 2 (TMI-2)-like accident. In this regard, this cooperative research project seeks to help the NRC to assess S/R5/M3.3 associated with case studies of the TMI-2 lower-head creep rupture. The results of the simulations clearly demonstrate that the TMI-2 lower-head failure occurs. Thus, solely using the S/R5/M3.3 models of the molten pool and debris-to-vessel contact resistance, without implementing the gap cooling model, cannot explain the conservation of the TMI-2 lower head during the accident. These studies also conclude that the results calculated with the UNIX and Microsoft PC versions of S/R5/M3.3 are comparable, and hydrogen productions as well as lower-head creep ruptures vary with different time steps for the alternative accident. Further, those results for the base case and alternative accident are alike; thus, the models cannot differentiate between the base-case and alternative accident scenarios.