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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
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
Ukraine releases video of Russian “kamikaze” drones flying near nuclear plant
New reports allege Russia is flying kamikaze drones and firing small arms near the site of Ukraine’s Zaporizhzhia nuclear power plant. Europe’s largest such facility, Zaporizhzhia has been under Russian control since 2022.
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.