ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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!
Latest Magazine Issues
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
NWTRB to hold public meeting on SNF disposal and corrosion
The Nuclear Waste Technical Review Board, an independent federal agency that evaluates the Department of Energy’s efforts to manage and dispose of spent nuclear fuel and high-level radioactive waste, will hold a two-day public meeting May 21–22 to review information on the DOE’s research and development activities related to the disposal of SNF and HLW in crystalline host rocks and on the corrosion of commercial SNF after disposal.
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.
