ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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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March 2023
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February 2023
Latest News
Savannah River facility prepped for NNSA project
Work has begun to prepare the Savannah River Plutonium Processing Facility (SRPPF) at the Department of Energy’s Savannah River Site in South Carolina for its future national security mission: the manufacturing of plutonium pits for the National Nuclear Security Administration.
Yang Tang, Yangping Zhou, Zhiwei Zhou, Lei Shi
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 27-44
Technical Paper | doi.org/10.1080/00295450.2017.1352329
Articles are hosted by Taylor and Francis Online.
Different from most current commercial nuclear power plants, the High-Temperature gas-cooled Reactor Pebble-bed Module (HTR-PM) power plant consists of two reactor modules connected to a common steam turbine system that will bring a special coupling effect between the two reactor modules. An engineering simulator of the HTR-PM plant was developed by embedding the THERMIX/BLAST code into the vPower simulation platform. Two sets of nuclear steam supply systems of HTR-PM, including two reactors, two steam generators, two helium blowers, and the helium flow ducts, were simulated by two THERMIX/BLAST code modules, respectively. The entire secondary loop system was simulated using intrinsic models of the vPower simulation platform. The vPower platform connects and synchronizes the two THERMIX/BLAST modules, as well as the simulation module for the secondary loop system. The engineering simulator was applied to simulate the behavior of HTR-PM under steady-state operation, startup and shutdown processes, and accident conditions. The coupling effect during the condition conversion process and the thermal characteristics under accident conditions of HTR-PM were analyzed by the engineering simulator.