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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Heikki Kantee, Harri Tuomisto, Vesa Yrjölä
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 308-315
Technical Paper | RELAP/MOD2 / Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34396
Articles are hosted by Taylor and Francis Online.
The RELAP5/MOD2 computer code has been extensively utilized in calculation of thermal-hydraulic sequences concerning the pressurized thermal shock safety issue in the Loviisa 1 nuclear power plant. The cases analyzed feature stuck-open pressurizer safety valve sequences, small hot-leg breaks, steam line breaks, and, in one case, a primary-secondary leakage. The main purpose of these analyses is to validate and compare the results from the full-scale Loviisa training simulator analyses. The RELAP5 model is made to the detail allowed by the computer. It includes a description of primary and secondary circuits as well as modeling of the emergency core cooling and control systems. Single-phase thermal stratification and mixing are essential phenomena when pressurized thermal shock sequences are analyzed. The capabilities of the large system analysis code to predict these phenomena in the reactor circuit are discussed.