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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Energy is everything
Lisa Marshallpresident@ans.org
Energy is the foundation of modern society. It enhances quality of life and drives industrialization. As we work toward fuller energy transition, policies are essential to organizing our march forward. Bipartisan legislation is doing just that, propelling our current and future actions.
The Accelerating Deployment of Versatile, Advanced Nuclear for Clean Energy (ADVANCE) Act will help propel the work of industry, academia, and several branches of government in exciting—and necessary—directions.
The Senate introduced the act in March 2023, and the House of Representatives passed the Fire Grants and Safety Act, which incorporated the ADVANCE Act, on May 9, 2024 (393–13). Then on June 18, the Senate passed the ADVANCE Act (88–2), and on July 9, President Biden signed the bill into law. New and revised approaches to process and deployment of nuclear energy capacity is well on its way. Below, I have highlighted a few title sections to show scope and significance.
John C. Wagner, Alireza Haghighat, Bojan G. Petrovic
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 373-398
Technical Paper | Radiation Protection | doi.org/10.13182/NT96-A35241
Articles are hosted by Taylor and Francis Online.
The application of Monte Carlo methods for reactor pressure vessel (RPV) neutron fluence calculations is examined. As many commercial nuclear light water reactors approach the end of their design lifetime, it is of great consequence that reactor operators and regulators be able to characterize the structural integrity of the RPV accurately for financial reasons, as well as safety reasons, due to the possibility of plant life extensions. The Monte Carlo method, which offers explicit three-dimensional geometric representation and continuous energy and angular simulation, is well suited for this task. A model of the Three Mile Island unit 1 reactor is presented for determination of RPV fluence; Monte Carlo (MCNP) and deterministic (DORT) results are compared for this application; and numerous issues related to performing these calculations are examined. Synthesized three-dimensional deterministic models are observed to produce results that are comparable to those of Monte Carlo methods, provided the two methods utilize the same cross-section libraries. Continuous energy Monte Carlo methods are shown to predict more (15 to 20%) high-energy neutrons in the RPV than deterministic methods.