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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
April 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
IAEA project aims to develop polymer irradiation model
The International Atomic Energy Agency has launched a new coordinated research project (CRP) aimed at creating a database of polymer-radiation interactions in the next five years with the long-term goal of using the database to enable machine learning–based predictive models.
Radiation-induced modifications are widely applicable across a range of fields including healthcare, agriculture, and environmental applications, and exposure to radiation is a major factor when considering materials used at nuclear power plants.
P. Kar, G. Danko, J. S. Armijo, M. Misra, D. Bahrami
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 90-104
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3748
Articles are hosted by Taylor and Francis Online.
Thermal analysis of an alternative boiling water reactor (BWR) waste package design for permanent disposal in the Yucca Mountain Repository is reported in this paper. The new design implements an increase in the holding capacity of the BWR waste packages from 44 to 52 assemblies and a modified arrangement sequence of waste packages in the emplacement drift. The design is favorable from the perspective of a generally drier emplacement drift due to an increase in heat load in the waste packages and the resulting higher temperatures. The analysis addresses heat transfer issues inside the waste package and those pertinent to satisfying the safe thermal limits for the waste package components. Key parameters in the analysis are the spent nuclear fuel assembly effective conductivities, the number of aluminum shunts, and the gap backfill with pressurized helium inside the waste packages. The feasibility of the proposed design is demonstrated by the internal waste package thermal model and the thermal-hydrologic environment in the emplacement drift. The conformity of the alternative thermal design to safe temperatures, in spite of the additional heat load, led to another innovative design with radial arrangement of assemblies in the waste packages that would further support the sustenance of drier emplacement drifts. These radial configurations are also discussed in this paper.