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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
Joseph A. Naser
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 313-328
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33199
Articles are hosted by Taylor and Francis Online.
The RETRAN-01 system thermal-hydraulics analysis code has been used to simulate the Peach Bottom Unit 2 boiling water reactor (BWR) turbine trip tests. Since these studies have been performed, a second version of the code, RETRAN-02, has been developed and released. The RETRAN-02 code has a number of physical models that did not exist in RETRAN-01. These include slip between phases, subcooled voiding, special steam separator, one-dimensional kinetics, and iterative numerics models. The new models that exist in RETRAN-02 allow a more realistic modeling of the physical phenomena that occur, in particular, in a BWR. The effect of these new models is studied through the analysis of one of the Peach Bottom turbine trip tests. Each model’s effect is easily observed since the models are applied one at a time. It was demonstrated that if the same options are used in both RETRAN-01 and RETRAN-02, essentially the same results are obtained. This is important because of the large amount of validation that has been performed with RETRAN-01. The results using the new models demonstrate that they are capable of more realistically describing the physical phenomena that occur during a turbine trip in a BWR.