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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.
C. Villagrasa, J. Darréon, I. Clairand, F. Quéinnec
Nuclear Technology | Volume 168 | Number 1 | October 2009 | Pages 149-153
Dose/Dose Rate | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 1) / Radiation Protection | doi.org/10.13182/NT09-A9116
Articles are hosted by Taylor and Francis Online.
Evaluation of the radiological protection quantity E requires determining the dose deposited in different organs and tissues. This is why monitoring in exposed workplaces is ensured by dosimeters that are worn on the trunk and calibrated to measure the personal dose equivalent Hp(10) as an estimator of the effective dose E. However, the characteristics of the instrumentation and the definition of Hp(10) itself can result in significant differences between these two quantities. The Institute for Radiological Protection and Nuclear Safety Laboratory of Dosimetry for Ionizing Radiation in France is currently developing an instrumented anthropomorphic dummy allowing the evaluation of the effective dose for photon irradiation fields. For neutron fields, a preliminary numerical study has been done. The calculations were made using a mathematical anthropomorphic phantom, and the transport of irradiating particles was calculated using the Monte Carlo code MCNPX. The numerical study has been validated, and the results of some standard irradiations and differences between the effective dose and its estimator have been calculated for various realistic workplace simulations.
