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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.
Joel McDuffee, Rich Christensen, Daniel Eichel, Mike Simpson, Supathorn Phongikaroon, Xiaodong Sun, John Baird, Adam Burak, Shay Chapel, Joonhyung Choi, Jacob Gorton, D. Ethan Hamilton, Dimitris Killinger, Sam Miller, Jason Palmer, Christian Petrie, Daniel Sweeney, Adrian Schrell, James Vollmer
Nuclear Science and Engineering | Volume 196 | Number 1 | October 2022 | Pages S234-S259
Technical Paper | doi.org/10.1080/00295639.2021.2017663
Articles are hosted by Taylor and Francis Online.
The mission of the Versatile Test Reactor (VTR) is to enable accelerated testing of advanced reactor fuels and materials as required for advanced reactor technologies. Each advanced reactor type has unique challenges, and these challenges affect the design of the testing vehicles used for accelerated testing. For molten salt reactor testing, some of the key focus areas are (1) understanding the complex thermal-hydraulic systems and materials that will facilitate heat removal from the reactor core, (2) mitigating the corrosion-associated issues that arise from using these materials at high temperatures, and (3) understanding how to measure and control salt composition/chemistry and properties during irradiation. This paper details the progress made toward surmounting these challenges to support future molten salt cartridge experiments in the VTR. Broadly, this work involves two major thrusts: design and analysis of an operating cartridge loop, and development of the instrumentation and control system needed to operate the loop successfully.