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What’s reshaping nuclear licensing and compliance today?
Mark Reidmeyer
It is the convergence of urgency, innovation, and modernization that is reshaping nuclear licensing and compliance today.
For decades, nuclear licensing operated in a relatively stable environment built around large light water reactors, predictable review cycles, and well-established regulatory pathways. Today, that model is evolving rapidly. Advanced reactors, AI-enabled tools, digital engineering platforms, grid reliability concerns, and aggressive decarbonization goals are all pushing the industry—and regulators—to move faster and think differently.
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.