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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
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.