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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
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
NRC wants input on Hermes 2 test reactor construction permit
The Nuclear Regulatory Commission is seeking input on its draft environmental assessment and draft finding of no significant impact for Kairos Power’s application to build the Hermes 2 test reactor facility in Oak Ridge, Tenn.
C. Vaglio-Gaudard, A. Santamarina, D. Bernard, G. Noguère, J. M. Ruggieri, J. F. Vidal, A. Lyoussi
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 267-275
Technical Paper | doi.org/10.13182/NSE09-103
Articles are hosted by Taylor and Francis Online.
The 56Fe international covariance matrices recommend variances for capture, elastic, and inelastic cross sections. Analysis shows that these matrices are often inconsistent and unrealistic. A new covariance matrix was established on the basis of feedback from the interpretation of two integral benchmarks representative of Generation III and Generation IV reflectors. Flux attenuation in the reflector at various energies demonstrates good agreement between calculation and experiment. The RDN code based on a nonlinear regression method using an iterative technique (limited to the first Gauss-Newton iteration in this study) was used to reestimate 56Fe cross sections and to deduce the a posteriori covariance matrix associated with the JEFF3.1.1 library. The results highlight that the 56Fe cross-section levels in the JEFF3.1.1 library are satisfactory. The new covariance matrix can then be used as a reference to calculate uncertainty propagation.