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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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
DOE issues final RFQ for WIPP clean energy initiative
The Department of Energy’s Office of Environmental Management has issued a request for qualifications for interested parties and prospective offerors looking to enter into a realty agreement for carbon-pollution-free electricity (CFE) projects at the department’s Waste Isolation Pilot Plant site in southeastern New Mexico.
Carlos E. Velasquez, Graiciany P. Barros, Claubia Pereira, Maria Auxiliadora F. Veloso, Antonella L. Costa
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 625-629
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-949
Articles are hosted by Taylor and Francis Online.
Different first wall material proposals based on tungsten alloy WNiFe, WLa2O3, W1.1TiC, W26Re, beryllium alloy S-B65, stainless steel SS316 and graphite have been studied in the last years. These materials must be capable of withstanding high temperature and neutron flux. Nevertheless, using hybrid systems, the first wall material choice could influence the criticality system due to the different properties of each material. To analyze this influence, two hybrid reactors were evaluated. The first one is a Tokamak based on magnetic confinement and the second one based on inertial confinement. Both systems contain a transmutation layer with reprocessed fuel spiked with thorium. The results showed the principal nuclides affected in the transmutation layer and the differences in the criticality due to neutron flux variations produced by the changes in the first wall material.