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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
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
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
Adel Alapour, Robert A. Hommerson
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 64-73
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33664
Articles are hosted by Taylor and Francis Online.
A dual recirculation pump trip (2-RPT) test, conducted as a part of the Edwin I. Hatch Nuclear Plant Unit 2 (Hatch-2) startup testing, is analyzed using onedimensional reactor kinetics and point reactor kinetics options in RETRAN-02 MOD002. The nuclear data utilized in RETRAN are obtained by SIMTRAN using the three-dimensional core simulator solution by SIMULATE (RTS/7), taking into account exposure and the steady-state core conditions prior to the test. Scram does not occur during this test despite the actual sensed water level rise of ∼43 cm (water level had initially been lowered), while core power, flow, and pressure continue dropping until the natural circulation establishes a new equilibrium condition at a lower reactor power level. A combined interaction of system components is taken into account in the analysis by interfacing a detailed hydraulic model of the system, with control system models for feedwater flow and steam line pressure regulation using actual plant settings. Analysis of the actual data recorded during the 2-RPT test indicates good agreement between measured and calculated parameters. It is also demonstrated that in spite of rather large changes in the axial power distribution with time, as predicted by onedimensional reactor kinetics compared with that of the point kinetics model, a good overall agreement is reached.