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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
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
Peters
Latta
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.
E. Privas, P. Archier, C. De Saint Jean, G. Noguere, J. Tommasi
Nuclear Science and Engineering | Volume 182 | Number 3 | March 2016 | Pages 377-393
Technical Paper | doi.org/10.13182/NSE15-21
Articles are hosted by Taylor and Francis Online.
The PROFIL and PROFIL-2 experiments were carried out in the fast reactor PHENIX. They were designed to provide integral information on neutron cross sections [(n,γ), (n,2n), and (n,f)] of several fission products and actinides. Previous interpretations report integral results with unrealistic small uncertainties that only take into account the statistical contribution. This work presents an uncertainty propagation technique able to include systematic uncertainties due to neutron fluence scaling. Such a technique consists of marginalizing analytically the uncertainties of the nuclear data (nuisance parameters) involved in the fluence scaling procedure. For the capture cross sections of 235U, 238U, and 239Pu, the interpretation of the PROFIL and PROFIL-2 experiments with the international library JEFF-3.1.1 provides excellent C/E results equal to 1.000, 1.019, and 0.982, respectively, with a relative uncertainty close to 1.5% (1σ).