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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Gary S. Was, Ronald Christensen, Chang Park, Richard W. Smith
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 445-457
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33697
Articles are hosted by Taylor and Francis Online.
A set of statistical patterns characterizing the conditions for failure of Type 304 stainless steel clad light water reactor fuel is formulated using a 450-assembly cycle data base from the Connecticut Yankee reactor and an information-theoretic (entropy) criterion of pattern formation. The pattern files, consisting of features formulated from output data obtained from the deterministic fuel performance code FCODE-BETA/SS, are partitioned into five failure and six nonfailure patterns. The failure probabilities of the patterns span the 0.17 to 37.47% range, as compared with the data base average of 2.86%. Features that contribute to failure patterns include large swings in the linear power at high burnup, frequent stress cycling at the ridge, and low coolant pH at high linear power. Contributing to nonfailure are low fission gas release, high axial uniformity in linear power, peak burnup, and clad creep strain at the ridge. The feature describing cycling of the linear power agrees qualitatively with previously identified factors contributing to failure of stainless steel clad fuel in the Connecticut Yankee reactor. From an operational standpoint, the fuel failure probability can be reduced by minimizing the number and magnitude of power ramps and maintaining a neutral coolant pH.