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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
Sang Yong Lee, Jae Jun Jeong, Si-Hwan Kim, Soon Heung Chang
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 177-187
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT99-177
Articles are hosted by Taylor and Francis Online.
The best-estimate thermal-hydraulic codes RE-LAP5/MOD3 and COBRA-TF were adopted to the Apollo DN 10000 workstation and subsequently merged. This was done to combine the excellent features of the two codes and thus produce a code with much enhanced capability. The resulting code was named COBRA /RELAPS. This code has features in common with COBRA/TRAC or TRAC-PF1: three-dimensional reactor vessel and one-dimensional loop modeling capability. The merging of the two codes is focused on the hydrodynamic model and numerical solution schemes. In COBRA/RELAP5, the system pressure matrices of the two codes are merged and solved simultaneously. The merged COBRA/RELAP5 calculations are done in process-level parallel mode on the Apollo DN10000 computer with two central processing units. Through various test simulations, the merging scheme and its implementation were proven to be valid. Thus, the code predictability is presumed eventually to depend on the generic capabilities of COBRA-TF and RELAP5/MOD3. However, to evaluate the overall code capability of COBRA /RELAP5, a systematic assessment should be done, including multidimensional effect tests.