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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Tank waste operations resume at Idaho’s IWTU
The Department of Energy’s Office of Environmental Management announced yesterday that waste processing operations have resumed at the Integrated Waste Treatment Unit (IWTU) at the Idaho National Laboratory Site. The resumption of operations follows the completion of two maintenance campaigns at the radioactive liquid waste treatment facility.
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.