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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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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.
David P. Hartmangruber, Bojan Petrovic
Nuclear Technology | Volume 175 | Number 1 | July 2011 | Pages 187-197
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/NT10-165
Articles are hosted by Taylor and Francis Online.
IRIS is an advanced, smaller-power pressurized water reactor, with aggressive dose reduction objectives. Because of its integral configuration, IRIS has a thick downcomer region that significantly reduces the radiation field outside the reactor vessel, forming the technical basis for achieving the objectives. However, this feature also makes the shielding analysis very challenging. The goal of evaluating the dose rate distribution throughout the IRIS nuclear power plant and, in particular, in all accessible areas further amplifies the problem.The MAVRIC sequence of the SCALE6 code system was selected for this analysis. MAVRIC employs a hybrid deterministic-stochastic approach, with CADIS and Forward-CADIS methods being used to develop variance-reduction parameters for Monte Carlo simulations. MAVRIC was successfully applied to determine the dose rate distribution throughout a large portion of the IRIS nuclear power plant including the control room. The obtained results confirmed that the dose rate is below the set target limit in the relevant plant areas and, in particular, in the control room.