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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Anek Kumar, Umasankari Kannan, S. Ganesan
Nuclear Science and Engineering | Volume 194 | Number 1 | January 2020 | Pages 32-43
Technical Paper | doi.org/10.1080/00295639.2019.1645502
Articles are hosted by Taylor and Francis Online.
The general geometry continuous-energy Monte Carlo code M3C is currently under development at the Bhabha Atomic Research Centre for reactor physics calculations. The development of the Monte Carlo code M3C for reactor design entails the use of continuous-energy nuclear data and Monte Carlo simulations for each of the neutron interaction processes. This paper describes the current status of the development of the code. The performance and accuracy of the code in application to a variety of problems have been investigated. The important features of this code are treatment of heterogeneous lattices by general geometry, use of point cross sections along with unionized energy grid approach, thermal scattering model for low-energy treatment, probability table treatment in unresolved resonance range, and capability of handling the microscopic fuel particles (TRISO) dispersed randomly, which is very useful in modeling high temperature gas-cooled reactor fuels. Apart from all of the important features in any Monte Carlo code available worldwide, the M3C code has an advanced capability to handle the geometry, which is not described by mathematical equations but only represented by the geometrical points. The code has been validated for its accuracy against a large number of sample problems covering a wide range from simple (like spherical) to complex geometry (like pressurized heavy water reactor lattice) and including randomly dispersed TRISO fuel particle systems. The code is presently restricted to assembly-level calculations.