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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.