ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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 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!
Latest Magazine Issues
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT announces nuclear manufacturing plant expansion
BWX Technologies announced today plans to expand and add advanced manufacturing equipment to its manufacturing plant in Cambridge, Ontario, Canada.
A $36.3 million USD ($50M CAD) expansion will increase the plant’s size by 25 percent—to 280,000 square feet—and another $21.7 million USD ($30M CAD) will be spent on new equipment to increase and accelerate its output of large nuclear components. The investment will increase capacity and create more than 200 long-term jobs for skilled workers, engineers, and support staff, according to the company.
Bei Ye, Jeff Rest, Yeon Soo Kim, Gerard Hofman, Benoit Dionne
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 27-40
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-56
Articles are hosted by Taylor and Francis Online.
DART (Dispersion Analysis Research Tool) is a computational code developed for integrated simulation of the irradiation behavior of aluminum dispersion fuels used in research reactors. The DART computational code uses a mechanistic fission gas behavior model and a set of up-to-date empirical correlations to simulate the fuel morphology change as a function of burnup. Integrating a thermal calculation subroutine enables fuel material properties to be updated at each time step. This paper describes the primary physical models that form the basis of the DART computational code. A baseline validation was performed through the modeling of several U-Mo/Al mini-plate tests (RERTR-6, 7, and 9) in the Advanced Test Reactor (ATR). A demonstration problem is also presented through the calculation of fuel plate swelling and constituent volume fractions in full-sized plates from the AFIP-1 test in ATR.