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Division Spotlight
Mathematics & Computation
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.
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
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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.
Trevor L. Cook, Steven M. Mirsky
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 166-171
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33907
Articles are hosted by Taylor and Francis Online.
As a part of the U.S. Nuclear Regulatory Commission’s unresolved safety issue A-45 decay heat removal program, the Los Alamos National Laboratory (LANL) performed a TRAC-PF1 simulation of the Calvert Cliffs Unit 1 pressurized water reactor in a cooldown to residual heat removal (RHR) entry conditions after a loss of off-site power (LOSP). A detailed four-loop TRAC model developed for the A-49 pressurized thermal shock program was used. The LANL results indicated an inability to both cool down and depressurize the primary system sufficiently to meet RHR entry conditions using only the atmospheric dump valves and auxiliary pressurizer spray. A RETRAN-02/MOD3 analysis was performed for the same transient, using assumptions consistent with those in the LANL analysis. A fast-running one-loop RETRAN model was selected because of the inherent symmetry of the transient. The RETRAN results compared well with sensitivity analyses indicating that the pressurizer model dominates the transient signatures. A best estimate RETRAN analysis of the cooldown was performed using a more accurate set of assumptions to better understand actual plant operational responses. These results indicate that RHR entry could be achieved after an LOSP using only existing plant equipment and procedures.