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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Take steps on SNF and HLW disposal
Matt Bowen
With a new administration and Congress, it is time once again to ponder what will happen—if anything—on U.S. spent nuclear fuel and high-level waste management policy over the next few years. One element of the forthcoming discussion seems clear: The executive and legislative branches are eager to talk about recycling commercial SNF. Whatever the merits of doing so, it does not obviate the need for one or more facilities for disposal of remaining long-lived radionuclides. For that reason, making progress on U.S. disposal capabilities remains urgent, lest the associated radionuclide inventories simply be left for future generations to deal with.
In March, Rick Perry, who was secretary of energy during President Trump’s first administration, observed that during his tenure at the Department of Energy it became clear to him that any plan to move SNF “required some practical consent of the receiving state and local community.”1
R. E. Simpson
Nuclear Technology | Volume 3 | Number 8 | August 1967 | Pages 500-506
Technical Paper and Note | doi.org/10.13182/NT67-A27782
Articles are hosted by Taylor and Francis Online.
A study has been made of the response of normal lithium fluoride and that depleted of 6Li when exposed to pure gamma rays and to the mixed neutron-plus-gamma fields of reactors. Results from a study of the glow curves of the two materials after gamma-ray exposure are similar. However, after reactor exposures in a known field of thermal neutrons and gamma rays, significant differences were found in the 200 and 275°C glow peaks for approximately the same integrated area under the curves. Presumably these are principally due to differences in the specific ionization of recoil electrons from gamma rays relative to that of the alpha particles and 3H recoils from the 6Li(n,α)3H reaction. By using thermal-neutron shields of 6Li or cadmium, the pure gamma dose can be obtained from the usual gamma-ray glow curves from either material. The response (integrated light output) of the depleted LiF per 1010 n/cm2(th) equals that caused by 0.7 rad of 60Co gamma rays, while the corresponding response of the normal phosphor exceeds that from 200 rad of gamma rays. Having determined the response of these materials to thermal neutrons, and considering the relative independence of the response (per rad) upon gamma-ray energy, one may use the depleted phosphor to determine gamma-ray dose within a reactor environment and the normal material as an auxiliary thermal-neutron-plus-gamma-ray detector.