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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
NWMO to select Canadian repository site this year
Canada’s Nuclear Waste Management Organization, a not-for-profit organization responsible for the long-term management of the country’s intermediate- and high-level radioactive waste, is set to select a site for a deep geologic repository by the end of the year.
A. K. Sengupta, J. Banerjee, T. Jarvis, T. R. G. Kutty, K. Ravi, S. Majumdar
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 260-269
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT03-A3388
Articles are hosted by Taylor and Francis Online.
Hyperstoichiometric uranium-plutonium mixed carbide fuel (U0.3Pu0.7)C1+x has been the driver fuel for the sodium-cooled Fast Breeder Test Reactor (FBTR) at Kalpakkam, India. The existing core is being slowly expanded by substituting the earlier fuel with hyperstoichiometric (U0.45Pu0.55)C1+x fuel for operation of the reactor at full power [40 MW(thermal)] and at higher linear heat rating of the fuel. To evaluate the fuel in terms of its in-reactor performance, some of the important out-of-pile thermophysical and thermomechanical property data like the coefficient of thermal expansion, thermal diffusivity, thermal conductivity, and hot hardness have been generated as a function of temperature. The out-of-pile chemical compatibility of the fuel with Type 316 stainless steel (20% cold-worked) cladding material has also been established experimentally. From the data generated in these measurements, it has been concluded that with this fuel the reactor could be operated at full power with a fuel linear heat rating of 400 W/cm. Out-of-pile compatibility experiments indicate that carburization of the clad by carbon transfer from the fuel would not be severe to cause any breach of clad during the residence time of the fuel in the reactor.