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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Behrooz Khorsandi, Mehdi Reisi Fard, Thomas E. Blue, Don W. Miller, Wolfgang Windl
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 208-220
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT07-A3866
Articles are hosted by Taylor and Francis Online.
Focusing on the gas turbine-modular helium reactor (GT-MHR), we have developed methods to predict the positions in a nuclear reactor where silicon carbide (SiC) semiconductor diode detectors may work functionally as neutron monitors for at least one refueling cycle. Using MCNP and TRIM, we determined the count rate due to fast neutron-induced primary knock-on atoms and tritons, and the number of displacement damage defects that are created per count and over a refueling cycle, for SiC diode detectors placed at four different radial locations in the central reflector of the GT-MHR. We found that although the total count rates for the SiC detectors placed in locations close to the fuel elements were highest (~1.2 × 106 counts/s), at those locations the detectors cannot tolerate the damage caused by fast neutrons for a reactor refueling cycle. On the contrary, for SiC detectors placed at the center of the central reflector, where the thermal neutron flux is the dominant flux component, the detectors can survive a GT-MHR refueling cycle. At this location, the total count rate for the SiC diode detectors that we have analyzed is ~1.6 × 105 counts/s.