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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.
Parvez Salim, Yassin A. Hassan
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 275-285
Technical Paper | RELAP/MOD2 / Nuclear Safety | doi.org/10.13182/NT90-A34393
Articles are hosted by Taylor and Francis Online.
A best-estimate small-break loss-of-coolant accident (SBLOCA) analysis of a four-loop pressurized water reactor nuclear power plant is conducted using the computer code RELAP5/MOD2. A plant-specific RELAP5 model is developed, and steady-state operating conditions are calculated. The steady-state model is then employed to obtain SBLOCA scenarios for different break sizes. Transients resulting from the different breaks are studied to determine the limiting break size and obtain comprehensive transient scenarios. The effect of the hydraulic diameter on the transient behavior, related to the steam generator U-tubes, is also observed. The relationship between the break size and the peak cladding temperature is obtained. The study indicates that as the break size increases, a smaller core inventory instigates heatup during core boil-off.
