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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Germany’s Unterweser completes removal of steam generators
All four steam generators at Germany’s Unterweser nuclear power plant have been removed from the reactor building, plant owner PreussenElektra has announced. The single-unit pressurized water reactor was shut down in 2011 as part of Germany’s decision to phase out nuclear energy. Decommissioning and dismantlement of the reactor began soon after PreussenElektra was granted a permit for the work in February 2018.
T. Shimooke, K. Matsumoto
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 119-130
Technical Paper | Fuel | doi.org/10.13182/NT77-A31855
Articles are hosted by Taylor and Francis Online.
The probability distributions of the peak-clad temperature (PCT) and of the maximum cladding oxidation thickness supposed to occur in the hypothetical loss-of-coolant accidents (LOCAs) for a typical boiling water reactor (BWR) are studied by a computer-simulated experiment, using the computer program MOXY-EM, one of the fuel heatup analysis codes for a BWR. To reduce the numbers of the computer runs, the theory and techniques of the factorial design of experiments are used. We have specially developed the partially orthogonal factorial design, which not only selects the small fraction of all possible runs that correspond to the various input sets, but also produces under this small number of runs the right statistical distributions of the PCT and of the cladding oxidation thickness. The PCT is found statistically to distribute normally, and the maximum cladding oxidation thickness obeys the log-normal distribution in our survey for the LOCAs at a typical BWR.