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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
September 2024
Nuclear Technology
August 2024
Fusion Science and Technology
Latest News
Comanche Peak adds years to operating licenses
The Nuclear Regulatory Commission has renewed the operating licenses of Comanche Peak Units 1 and 2 for an additional 20 years.
Unit 1’s operating license now expires on February 8, 2050, and Unit 2’s on February 2, 2053.
Mitsuo Shindo, Akira Tsuruo, Shun-ichi Miyasaka, Mitsuyuki Kitazume, Jun-ichi Miyakoshi
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 450-463
Technical Paper | doi.org/10.13182/NSE67-A18284
Articles are hosted by Taylor and Francis Online.
The transmission of gamma rays through a straight cylindrical duct from an infinite plane source has been studied both theoretically and experimentally. The distribution of the resulting dose in the vicinity of the duct was calculated by the ray-analysis method, with the exception that the dose arising from radiation scattered within the duct was calculated by a semi-analytical Monte Carlo method. These results, together with those from experiments, lead to useful conclusions. Data applicable to the design of small ducts through shields have been developed for a range of various geometric parameters.