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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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
Why should safeguards by design be a global effort?
Jeremy Whitlock
I can’t think of a more exciting time to be working in nuclear, with the diversity of advanced reactor development and increasing global support for nuclear in sustainable energy planning. But we can’t lose sight of the need to plan for efficient international safeguards at the same time.
Global nuclear deployment has been underpinned since 1970 by the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), making it a key customer requirement for governments to demonstrate unequivocally that the technology is not being misused for weapons development.
The International Atomic Energy Agency (IAEA) has helped verify this commitment for more than 50 years, but it has never safeguarded many of the advanced reactors (and related fuel cycle processes) being developed today.
D. Rochman, A. J. Koning
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 265-279
Technical Paper | doi.org/10.13182/NSE11-37
Articles are hosted by Taylor and Francis Online.
This paper presents new evaluations for the two natural isotopes of copper from thermal neutron energy up to 200 MeV, including covariances. The evaluation and adjustment method consists of applying a Monte Carlo method to select the model parameters to obtain better agreement with differential data, criticality safety, and fusion benchmarks. In the resonance range, the latest resonance parameters and uncertainties are adopted. In the fast neutron range, the TALYS reaction code is used to calculate all nuclear data quantities and covariances. The proposed evaluations present important improvements for fusion benchmarks compared to the current libraries. These new evaluations of 63Cu and 65Cu are proposed for the JEFF-3.2 European nuclear data library. As a spinoff, correlations between cross sections and benchmarks can be obtained.