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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.
Werner Schöck, Helmut Bunz, Robert E. Adams, Melvin L. Tobias, Frank J. Rahn
Nuclear Technology | Volume 81 | Number 2 | May 1988 | Pages 139-157
Technical Paper | Nuclear Aerosol Science / Nuclear Safety | doi.org/10.13182/NT88-A34089
Articles are hosted by Taylor and Francis Online.
Aerosol behavior is a central topic in the overall determination of source terms of accidents in nuclear power plants. Aerosol behavior codes have been developed for ∼20 yr and their state of development is considered to be well advanced. The acceptance of results of the calculations, however, was poor as far as physical understanding and the results of basic research were involved. Proof that the codes are complete and the choice of models is adequate for a situation during an accident required large-scale integral experiments that simulated real conditions as closely as necessary and possible. Recently, three large-scale experimental programs were carried out dealing with the behavior of aerosols during core-melt accidents in light water reactors (LWRs). In the Nuclear Safety Pilot Plant (NSPP) program, the principal behaviors of different insoluble aerosols and of mixed aerosols were measured in dry air atmospheres and in condensing steam-air atmospheres contained in a 38-m3 steel vessel. The Demonstration of Nuclear Aerosol Behavior (DEMONA) program used a 640-m3 concrete containment model to simulate typical accident sequence conditions, and measured the behavior of different insoluble aerosols and mixed aerosols in condensing and transient atmospheric conditions. Part of the LWR Aerosol Containment Experiments (LACE) program was also devoted to aerosol behavior in containment; an 852-m3 steel vessel was used, and the aerosols were composed of mixtures of insoluble and soluble species. The results of these experiments provide a suitable data base for validation of aerosol behavior codes. Fundamental insight into details of aerosol behavior in condensing environments has been gained through the results of the NSPP tests. Code comparisons have been and are being performed in the DEMON A and LACE experiments.
