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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.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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NRC to host meeting on Davis-Besse plant performance
The Nuclear Regulatory Commission will discuss the Davis-Besse nuclear power plant safety performance last year in a public meeting this Thursday, August 29.
B. F. Myers, N. L. Baldwin, W. E. Bell
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 501-508
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31910
Articles are hosted by Taylor and Francis Online.
A review and analysis of available data on the release of fission gases from high-temperature gas-cooled reactor fuel particles indicates that the release of short-lived nuclides (half-life ≲5.3 days) occurs from the fissile material primarily by a mechanism involving recoil followed by gas-phase and bulk diffusion in the surrounding material at temperatures up to at least 1300°C (1573 K). The gas-phase contribution to the release of short-lived nuclides is dominant at temperatures below 600°C (873 K), and bulk diffusion is dominant at temperatures above 900°C (1173 K). Fission gas release to birth ratio (R/B) varies with half-life to a power of ∼0.2 at 300°C (573 K) and ∼0.5 at 1100°C (1373 K). For the short-lived isotopes, R/B is independent of burnup over the range from 0 to 63% FIMA in UC2 kernels; for dense ThO2 kernels, the data are insufficient to determine the burnup dependence. For the long-lived and stable isotopes, release from dense ThO2 kernels is strongly dependent on burnup. Iodine and tellurium isotopes may be treated as if they were xenon isotopes.