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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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R. L. Fleischer, P. B. Price and R. M. Walker
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 153-156
Technical Paper | doi.org/10.13182/NSE65-A20234
Articles are hosted by Taylor and Francis Online.
Thermal-neutron doses can be simply and inexpensively measured over many orders of magnitude of integrated flux by a count of induced-fission-damage tracks in a solid with uranium impurities. Examples are given of the use of a single ordinary glass to measure neutron flux from 3 × 1014 to 4 × 1018nvt and of the use of glass to measure the spatial variation of neutron flux. Other materials, either glassy or crystalline, allow a wide range of fluxes to be measured.
