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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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!
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Latest News
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
R. C. Lloyd, E. D. Clayton, C. R. Richey
Nuclear Science and Engineering | Volume 4 | Number 5 | November 1958 | Pages 690-697
Technical Paper | doi.org/10.13182/NSE58-A25556
Articles are hosted by Taylor and Francis Online.
The graphite diffusion length was measured as a function of temperature in a 101-inch cube of graphite. A water-cooled BF3 counter was used as the neutron flux detector, with additional measurements being made with gold and indium foils. The steady state neutron flux was furnished by means of four -gram, Ra-Be neutron sources. Measurements were taken over a range of temperature from 22°C to 600°C at intervals of about 50°C. The variation of diffusion length with temperature change is in good agreement with the calculated variation assuming a 1/υ cross section for graphite and a constant transport mean free path.