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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Yea-Kuang Chan
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 80-92
Technical Note | doi.org/10.1080/00295450.2017.1338879
Articles are hosted by Taylor and Francis Online.
The baseline and verification performance tests based on American Society of Mechanical Engineers (ASME) Performance Test Code 6 (PTC 6) for Maanshan Nuclear Power Station (MNPS) Unit 1 were successfully conducted prior to and after the replacement of a high-pressure turbine rotor. In order to verify that the actual improvement in electrical output resulting from this replacement meets the vendor’s guarantee, measurement uncertainty analysis of the thermal performance test was calculated. Two verification performance tests show that the deviation for the corrected heat rates of the two tests differs by only 0.11%, which therefore meets the ASME PTC 6 requirements where the deviation between two tests should be within 0.25%. Thus, the quality of the test results is acceptable. After accounting for the test uncertainty, the test results demonstrated that the improvement in gross electrical output compared to the baseline performance test is between 12.57 and 22.63 MW(electric), which is higher than the contract guarantee of 10.0 MW(electric). Moreover, the major parameters of the turbine cycle measured during verification performance tests have established a reference base for monitoring the plant operating performance and provide useful information to turbine cycle design for a nuclear power plant.