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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.
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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
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Song Hyun Kim, Do Hyun Kim, Jong Kyung Kim, Jea Man Noh
Nuclear Science and Engineering | Volume 178 | Number 1 | September 2014 | Pages 29-41
Technical Paper | doi.org/10.13182/NSE13-38
Articles are hosted by Taylor and Francis Online.
In order to avoid calculation bias and increase calculation efficiency, convergence of the fission source distribution (FSD) in Monte Carlo simulations is important. Numerous analysis methods have been developed and used for checking the fission source convergence. However, such schemes have low applicability to Monte Carlo codes or give low diagnostic accuracy. To address these limitations, a method to verify the fission source convergence using the average and standard deviation of fission source positions is proposed. To collect the fission site information, the MCNP5 code was modified, and position information was extracted. The accuracy and advantages of the proposed method were verified by solving Organisation for Economic Co-operation and Development/Nuclear Energy Agency benchmark problems with the modified MCNP5 code and comparing the results to those obtained with the Shannon entropy and the nine center distance sum approaches. The analysis shows that the proposed method has good applicability and exhibits high accuracy for verifying the convergence of the FSD. It is expected that the proposed scheme will be a valuable contribution to the field of the fission source convergence.