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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Argonne researching “climate-ready” nuclear plant design
Scientists at Argonne National Laboratory have partnered with Washington state–based Energy Northwest to look at alternative ways to cool nuclear reactors as climate change impacts relied-upon water sources.
Alessandro Del Novo, Emanuela Martelli
Nuclear Technology | Volume 193 | Number 1 | January 2016 | Pages 1-14
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NT14-152
Articles are hosted by Taylor and Francis Online.
The International Atomic Energy Agency established a Coordinated Research Project (CRP) for EBR-II shutdown heat removal tests (SHRT). The CRP aims at improving the design and the simulation capabilities in fast reactor neutronics, thermal hydraulics, plant dynamics, and safety analyses. This is achieved by benchmark analyses of protected (SHRT-17) and unprotected (SHRT-45r) loss-of-flow tests, from the EBR-II SHRT program. In this framework, ENEA has set up, applied, and is validating an integrated multiphysics approach, based on existing codes, for supporting the design and the safety analysis of Generation IV liquid-metal fast reactors. This paper outlines the rationale of the CRP participation, and it focuses on the qualification of a three-dimensional (3-D) thermal-hydraulic nodalization of EBR-II and on the assessment of RELAP5-3D code against the test SHRT-17. The nodalization models one by one the fuel assemblies of the core and of the extended core of the reactor for an efficient coupling with a 3-D neutron kinetic analysis code. The experimental data are presented and the thermal-hydraulic phenomena of test SHRT-17 are discussed, being the basis for assessing the code performance and for discussing its limitations. Blind and open calculation results are presented and discussed.