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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
Govinda S. Srikantiah
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 216-227
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34744
Articles are hosted by Taylor and Francis Online.
The development, validation, and applications of the VIPRE code are presented. The development of specifications for a reactor core subchannel thermal-hydraulics analysis code for utility applications in the evaluation of reactor safety limits during normal operation and accident scenarios is traced. The capabilities of the VIPRE-01 code based on a homogeneous equilibrium model of two-phase flow with algebraic slip are presented along with a discussion of the extensive verification and validation of the code. Utility applications of the code, which received a safety evaluation report from the U.S. Nuclear Regulatory Commission in 1986, in the areas of fuel reload safety analysis, critical heat flux correlation development and testing, thermal margin analysis, and core thermal-hydraulic analysis are presented. The functional specifications and the development of VIPRE-02, an advanced version of the code based on a two-fluid model of two-phase flow that is capable of simulating the reactor core, vessel, and internal structure, are also described. A discussion of the developing applications for VIPRE-02, such as boiling water reactor instability analysis and pressurized water reactor steamline break analysis, is given with some initial results.