ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
Latest News
DOE, General Matter team up for new fuel mission at Hanford
The Department of Energy's Office of Environmental Management (EM) on Tuesday announced a partnership with California-based nuclear fuel company General Matter for the potential use of the long-idle Fuels and Materials Examination Facility (FMEF) at the Hanford Site in Washington state.
According to the announcement, the DOE and General Matter have signed a lease to explore the FMEF's potential to be used for advanced nuclear fuel cycle technologies and materials, in part to help satisfy the predicted future requirements of artificial intelligence.
J. B. Dragt, J. W. M. Dekker, H. Gruppelaar, A. J. Janssen
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 117-129
Technical Paper | doi.org/10.13182/NSE77-3
Articles are hosted by Taylor and Francis Online.
In the analysis of fission product reactivity worths, measured in the fast reactor spectra of the STEK critical-experiments facility, extensive use is made of a statistical method of cross-section adjustment. The principle is that adjustments are applied to the evaluated cross sections, as much as possible within their error limits and taking into account the existing correlations, in such a way that a better agreement between calculated and measured integral data is obtained. The method is briefly summarized in general terms, with some special applications needed for the STEK project. Then, a description is given of the practical realization for capture cross-section adjustment on the basis of reactivity worths of samples of fission product mixtures in different thicknesses measured in several fast reactor spectra. Details are given on the way the various contributions to the covariance matrix of group cross sections, including resonance selfshielding, are calculated for the fission product nuclides and for the mixtures. The paper only outlines the methods used; examples of applications can be found elsewhere. Finally, some limitations of the method and possible extensions in connection with standard nuclear data error files are discussed.