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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
Edward J. Waller, Jason T. Brown
Nuclear Technology | Volume 175 | Number 1 | July 2011 | Pages 93-104
Technical Paper | Special Issue on the 16th Biennial Topical Meeting of the Radiation Protection and Shielding Division / Radiation Transport and Protection | doi.org/10.13182/NT11-A12276
Articles are hosted by Taylor and Francis Online.
Handling radioisotope neutron sources may involve exposure to both neutron and gamma fields. Although the field of gamma dosimetry is well developed and reliable, challenges exist with personal neutron dosimetry. A number of gamma and neutron dosimeters were evaluated for their efficacy in providing personal dosimetry for radioisotope source manipulations. A commercial off-the-shelf electronic neutron dosimeter was observed to underestimate total operator dose when manipulating a 252Cf source. In this work, scaling factors were evaluated using both experimental results and Monte Carlo simulations to allow a measured electronic personal gamma dosimeter (EPGD) dose to be used to estimate the total neutron + gamma dose. The recommended scaling factor using an MGP SOR/R EPGD for free-field 252Cf is 18, and for shielded 252Cf the recommended scaling factor is 6. A conservative single scaling factor of 18 is appropriate for personal dosimetry estimates.
