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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
Michael Epstein, Hans K. Fauske
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 1021-1035
Late Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27694
Articles are hosted by Taylor and Francis Online.
It is postulated that the collapse of the upper debris bed was the main cause of core failure and core material relocation to the lower vessel plenum during the Three Mile Island Unit 2 (TMI-2) accident. It is shown that this mechanism of core relocation can account for the time scale(s) and energy transfer rate inferred from plant instrumentation. Additional analysis suggests that the water in the lower half of the reactor vessel was subcooled at the onset of relocation. Moreover, subcooling serves to explain the final coolable configuration at the bottom of the TMI-2 vessel. An important aspect of the analysis of the relocation event is that significant quantities of corium melt were not mixed with water at any one time, indicating an even lower likelihood of steam-explosion-induced vessel and containment failure than heretofore believed.