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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
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.
