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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Rafael de la Fuente, J. Manuel Dey, Pablo G. Sedano, Pedro Mata
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 169-185
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3023
Articles are hosted by Taylor and Francis Online.
The reload transient analysis methodology developed for the Cofrentes boiling water reactor-6, 2894-MW(thermal)-rated nuclear power plant is based on the RETRAN-03/MOD1 code. Cross-section files have been calculated with the CASMO-3/SIMULATE-3/SLICK codes. The system and hot-channel thermal-hydraulic responses have been predicted with the RETRAN-03 code, and the thermal margin for each fuel type has been determined by the TCPUIT code.Transient analyses are performed under several initial conditions to improve the plant operational flexibility. The two most thermal limiting plant transients were simulated: (a) generator load rejection with concurrent failure of the condenser bypass system and (b) failure of the feedwater flow control system to maximum demand. In addition, overpressure is evaluated with RETRAN-03, i.e., a closure of the main-isolation-valve transient.The Cofrentes tenth reload licensing analyses are verified against official fuel vendor calculations. The results obtained agree with them and cover the vendor thermal margins for the different fuel types considered.
