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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.