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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Bipartisan Nuclear REFUEL Act introduced in the U.S. House
To streamline the licensing requirements for nuclear fuel recycling facilities and help increase investment in nuclear energy in the United States, U.S. Reps. Bob Latta (R., Ohio) and Scott Peters (D., Calif.) have introduced the bipartisan Nuclear REFUEL Act in the House of Representatives.
The bill, introduced on December 6, would amend the definition of “production facility” in the Atomic Energy Act, clarifying that a reprocessing facility producing uranium-transuranic mixed fuel would be licensed only under 10 CFR Part 70. According to the lawmakers, this single-step licensing process would significantly streamline the licensing requirements for fuel recycling facilities.
Matthias Frankl, Rafael Macián-Juan
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 135-142
Technical Paper | doi.org/10.13182/NSE15-47
Articles are hosted by Taylor and Francis Online.
In radiation transport simulations, photonuclear processes still represent a rather new feature and are not as well established as neutron, electron, or other photon interactions. This study provides a benchmark for the photoneutron yields in C, Al, Cu, Ta, Pb, and U targets using the most current photonuclear cross-section library ENDF7U and the transport code MCNPX, v. 2.7. The isotopic material descriptions of C and Cu could be improved as more isotopes are available with the new library. The results were compared to experimental data provided by Barber and George [Phys. Rev., 116, 1551 (1959)]. In general, a good agreement can be observed although there seems to be a systematic underestimation in the calculated neutron yields.