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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Discovering, Making, and Testing New Materials: SRNL’s Center For Hierarchical Waste Form Materials
Savannah River National Laboratory researchers are building on the laboratory’s legacy of using cutting-edge science to effectively immobilize nuclear waste in innovative ways. As part of the Center for Hierarchical Waste Form Materials, SRNL is leveraging its depth of experience in radiological waste management to explore new frontiers in the industry.
Arántzazu Cuadra, José-Luis Gago, Francesc Reventós
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 41-48
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3485
Articles are hosted by Taylor and Francis Online.
Culminating in the participation of the Universitat Politècnica de Catalunya in the Organization for Economic Cooperation and Development-Committee on the Safety of Nuclear Installations/Nuclear Science Committee pressurized water reactor (PWR) main-steam-line-break (MSLB) benchmark, we present the analysis with RELAP/PARCS of a double-ended MSLB assumed to occur in the Ascó nuclear power plant (NPP). This Spanish NPP, a two-unit 1000-MW(electric) PWR plant of Westinghouse design, has been in normal operation since 1983. The utility uses the RELAP model developed by its analysts to study transients that occurred (or postulated), following its own procedures, giving response to operation-related issues, as well as serving licensing and training purposes. The model is well validated. The present study tests the RELAP/PARCS model of the Asco NPP and, in particular, tests the coupling between the neutronics and the thermal hydraulics; its focus is not licensing or validation.
