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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Former NRC commissioners lend support to efforts to eliminate mandatory hearings
A group of nine former nuclear regulatory commissioners sent a letter Wednesday to the current Nuclear Regulatory Commission members lending support to efforts to get rid of mandatory hearings in the licensing process, which should speed up the process by three to six months and save millions of dollars.
Chan Hyeong Kim, Jong Hwi Jeong, Sungkoo Cho, Sang Hyoun Choi, Min Suk Chung
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 345-348
Neutron Measurements | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9206
Articles are hosted by Taylor and Francis Online.
Neutron fluence-to-organ dose conversion coefficients (DCCs) were calculated for a Reference Korean-adjusted male voxel model, HDRK-Man, for some standard irradiation geometries of external neutron beams using the Monte Carlo radiation transport code MCNPX. The calculated values were compared with those for other models. The results show that HDRK-Man provides consistent results for the DCC values considering the differences in the voxel models.
