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
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Jeng-Ning Wang, Chung-Hsin Lu, Kuo-Wei Lee, Uei-Tyng Lin, Shiang-Huei Jiang
Nuclear Technology | Volume 168 | Number 1 | October 2009 | Pages 101-107
Dose/Dose Rate | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 1) / Radiation Protection | doi.org/10.13182/NT09-A9107
Articles are hosted by Taylor and Francis Online.
The site dose rate of a spent-fuel storage facility to the populace is a major concern in a radiation protection project. Shielding analysis of the facility must be performed to ensure that the nearby dose rates are within regulation limitations. The purpose of this study was to simulate an independent spent-fuel storage installation (ISFSI) storage facility with different methods and different conditions for validation and analysis. The discrete ordinates code DORT and the SKYSHINE III code were used for the cask surface flux estimation and the site dose rate calculation, respectively. The Monte Carlo code MCNP was also utilized to estimate the surface dose rate and site dose rate by its subsequent calculation. Various cask decay heats (23, 14, and 7 kW/cask) were considered as the source conditions. A facility layout composed of 30 casks was also simulated by the MCNP code and analyzed for the cask self-shielding effect to a certain detecting point. For a single storage cask, comparisons of the site dose rates calculated by different methods were carried out at variant distances. For the layout simulation, the calculated results indicated that the self-shielding effect could be roughly classified into several groups according to the location of the storage cask, and a factor could be assigned to each group. These classified factors might help to infer the site dose in variant layout designs. The site dose rates calculated by different codes were compared for the whole facility, too. In spite of the similar dose rates on the cask surface, the difference of site dose rates changes with decay heat. The layout study of the ISFSI facility could offer information to make the site dose estimation more efficient as many layout assessments are needed.
