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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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
K. M. Barry, J. A. Corbett
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 120-130
Technical Paper | Analysis | doi.org/10.13182/NT71-A30910
Articles are hosted by Taylor and Francis Online.
Experimental irradiations of pressure vessel materials were conducted at the Saxton reactor and Babcock & Wilcox Test Reactor to provide radiation effects data for fast neutron fluences up to 1 × 1020 n/cm2 (E > 1 MeV). Included in the capsule assemblies were 237Np and 238U dosimeters and 54Fe correlation monitors. The activities of the dosimeters were combined with the neutron spectrum calculations of a multigroup diffusion code to establish the fast-neutron (E > 1 MeV) fluences experienced by the dosimeters. For both reactors the fluences derived from the different dosimeters were in good agreement indicating both the adequaey of the spectral predictions and the successful application of the fission dosimeters. It is shown that the 237Np and 238 U dosimeters are responsive to a wider range of neutron energies than the more commonly used threshold detectors and are therefore better able to ensure the aptness of calculated neutron spectra. This effort has indicated that the use of 237Np and 238U dosimeters in power reactor vessel surveillance programs leads to more meaningful correlations between neutron fluence and induced radiation effects.